ML20205N512
| ML20205N512 | |
| Person / Time | |
|---|---|
| Issue date: | 05/06/1986 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Fraley R Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML20205N459 | List: |
| References | |
| FOIA-86-335 NUDOCS 8704030041 | |
| Download: ML20205N512 (109) | |
Text
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f't$ %, UNITED STATES
_ ;- S NUCLEAR REGULATORY COMMISSION
% 'c j WASHING TON. D. C. 20555
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s a nes MEM0PANDUlt FOR: Raymond F. Fraley, Executive Director f-Advistry Committee on Reactor Safeguards g FROM: Harold R. Denton, Director Office of Nuclear Reactor Regulation
SUBJECT:
CHERN0BYL REACTOR EVENT Enclosed for the ACRS' information are two copies of several papers discussing Soviet reactors.
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fffi'roldR.Denton, Director Office of Nuclear Reactor Regulation
Enclosures:
Index and Articles C_5 MP
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foi A- 66-335 8704030041 B70330 PDR FOIA TAYLORS6-335 PDR
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7
- 1
M INDEX OF ARTICLES
" Effectiveness of Emergency Cooling of Water-cooled Power Reactors,"
L. P. Kabanov, Thermal Engineering, 30 (2), 1983.
" Nuclear power in the Soviet Union," B. A. Semenov, IAEA Bulletin, Vol. 25 No. 2.
Graphite-water steam-generating reactor in the USSR," N. A. Dollezhal',
Nuclear Energy, Vol. 20, No. 5, October 1981.
" Experience in the Construction of Large Power Reactors in the USSR,"
N. A. Dollezhal' and I. Ya. Emel'yanov, Atomnaya Energiya, Vol. 40, No. 2 February 1976.
- " Nuclear Power and the Scientific-Technical Problems in its Development,"
g N. A. Dollezhal', Atomnaya Energiya, Vol. 44, No. 3, March 1978.
"Some Characteristics Of and Experience With the Operation of Nuclear Power Plants with RBMK-1000 High-Powered Water-cooled Channel Reactors (RBMK),
N. A. Dollezhal' et al. , Atomnaya Energiya, Vol. 54, No. 4, April 1983.
" Basic Approaches to Nuclear Power Station Safety in the USSR," V. A. Sidorenko et al., Atomnaya Energiya, Vol. 43, No. 5, November 1977.
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Thermal Engineering. 30 (2).1983 61 Teaastated from reproenerper.aa. 30.12) 4 10 t1983) U.D.C. 6t t.03g,sg Effectiveness of Emergency Cooling of Water cooled Power Reactors LP.KABANOV Moscowv Power Institute The scearing of safety of a nuclear power (NP) station is in our opinion. along with conducting investigations of such one of the necessary conditions of development of nuclear failures it is necessary to evaluate the effectiveness of emer-power engineering. The main protective system for VVER gency cooling under conditions of MCA of water-cooled power and RDstK ? reactors is that of cmcrgency cooling'. In analy- reactors ,
sis of the effectiveness of emergency cootmg one should bear Despite the fact that the concept " effectiveness" is fairly in mind both the emergency cooling systems and the organi- often used in relation to many units and systems, this term sation of heat removat in the reactor core with supply to it in relation to emergency cooling has not yet been fully I of emergency coolant. The emergency cootmg must help cope defined. in principle. effectiveness of emergency cooling can both with the consequences of a maximum credible accident be defined both on the basis of the limiting opproach. and on tMCA) caased by burst of a pipeline and with the conse- the basis of the statistical probability approach to securing quences of other failurcsl . safet y . In the first case, as a criterion one can select it should be noted that after the failure at the Three Mile limiting temperature of fuel element cans Tyn" manufactured Island-2 plant (USA) much attention is being paid to analysis of sitconium alloy which is normally established at 1473 K.
of emergency situations with relatively small leaks of coolant, The remaining demands made on emergency cooling of water-as a result of which separation is possible in the core of a moderated water-cooled retetors. formulated by the US water moderated water-cooled reactor. Nuclear Regulatory Commission' are mainly determined by the 1
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4 Figure 1. Basic diagram of the emergency cooling system of the core of the VVER 1000 reactor'. f) storage tanks:
- 2) steam generators; 3) eisin circulaten pumpsi di nitrogen supply linen 3) nitrogen discherge linet il lines for filling and emptying the storage tenhet y.13.ll) high pressure pumps for emergency cwlingt 8.12.16) low pressure pumps for 0 emergency cooling 9) tanke for emergency reserve of borsele seidt 10) Intermediate cooling loopt !!) cooling (service) water linet 141 heat exchangers for cooling of the coolant.
t VVER denotes a water moderated water cooled resetor, g g ., g g en } } {
RBMK e channel type urenlum graphite bolling reactor.
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02 Thermal Engineering. 30 (2).1983 les el of .ittained values of Ten. Thus, the lower Ten as RllMK-1000* reactors. Despite considerable difference in the wrv ued with T['f. the higher the cffcetiveness of emer- course of AICA in VVI.R and RllitK reactors the ECS of taoth gency emling. In the limiting case Tencan increase so reactors have common cicments (water supply in the first httle that the consequences nf MCA will essentially be reduced stage from tanks with suscquent change to feed from cmergency pumps electrically driven by diesel generators),
to the minimum. A situation of this kind was recorded on the esperimentat LOFT reactor (US A) when after testing with At present. in estimiten of safety the " limiting" approach samutation of MCA and subsequent emergency cor>Iing the fuct is adopted and the safc'y systems in particular of emer-gency coohng are designed on the basis of the principle of cice ents and the entire core were found to be without visible single failure' which dc: ermines the necessary degree of da- Me t Cembon Ten
- Ty combines the reliabihty of the emer- redundancy of the mam equipment of the ECS.
gency cooling system (l'CS) and the ideality of the cooling A very important probicm is selection of the rate of r*cdun*
prxesses in the reactor core. Thus. we speak of the united d.incy of the main sub's> stems of the ECSC. The interpreta-ECS-reactor system. therefore in relation to such a system tion of the single failure principle can be ambiguous, and its it is appropriate to discuss the structural rehability of the realisation depends on the selected approach. Let us examine FCs amt the techmcal ideahty of coohng of the enre. In t his prnposition using at examples different subsystems of lief 4 it is suggested that we consider togethor the relaatnhty the t'CSC of water-moderated water cooled reactors. First an<t technical ideahty as a more common property of the syv of all et shout <1 be noted that both the subsystem of passive tem , t.c. effectiveness of its functioning. The ef fectivenew inrectem and. c%pecial:. . the high pressure and low pressure of functioning can also be defined on the basis of statistical pumping mutriystems arc active protective systems, probabihty approach. Ref.4 proposes the following espres- it is possible to distanguish two groups of initial events for sici for the index of effectiveness of functioning E. which functioning of the subsystems of active injection: bursting subsequently we shall term the index of ECS cffectiveness: of the main circulation pipe and bursting of the pipe from the reactor to the nonreturn valve on the line between reactor
, f,u_sp ' gg, and nturage tank. In the first case the bursting of the oloc w he re PECS w indes of structural rehabihty of the function- ducs not affect the conungent failure of the elements of the l
ing subsysicm of the EC51 Pj* w probabihty of not ECSC and 6n accordance with the principle of single failure
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cicced.ng the hmeting temperature of the fuel element cans. " " " " Y ' # "'
or "thermotechnical stability" (in contrast to thermutechnical " * ""# ' " **
- rehability' which characterises the behaviour of fuct elements 6ts functions in 100% volume, then with failure of one of them under rated cooling conditions). the system can fully carry out its functions. The same nitnation occur,if the system of passive injection consists of three ch.unwtw with $nt capacity each.
" I" **'"""""# "' d" '";t ut event a burst of a pipe connecting
/ y 2J J2 y & W reartor with storage t.n* it follows that fadure of one of the
_ sinrage tanks depend on the 6nitial event. Should another it . _ A lA_ . . // - ,// _ *torage tank f.nl. mmplete f.nture of the subsystem of pas- l
_ sive oycetion occurs. if it consists of two storage tanks 110% .
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,q7 an c apacit y exh. If the nuhtyttem consists of three storage J,
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L-J MU f;g tanks $UL in capacity exh. partial failure of the system occurs. True, in this cise a pipe 250-300 mm in diameter I
UM: I '# M f '.h *,L.
h will burst. and not the auin pipe $00-900 mm in diameter.
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k Apparently for this reason. in the ECSC of water-moderated water cuoted reactors in the US A the subsystems of passive 4 7 'T Wfwa' *'
. Inject n n w consist of three storage tanks 50% each in i 6 4 I b capacit y .
A L ,
,q 7 , G.y in Sovict projects the gutisystem of passive inlcction has j g: -
four storage tanks with nnmin.at capacity of each of them of e l' '
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y
-r
$01. Water supply in combined t two tanks supply water to
- the aguce above the core. and two other tanks supply water i
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to the downcoming nection and then to the space under the i core, water supply from above is used mainly for rapid i Figure L Emergency cooling system of the Ril\tK 1000 reactor'. f) reactors 2) discharge headerst 3) distributive flooding of the up.ies under the core through the peripheral l group headers; el hydraulic cylinders of the subsystem of channels of the core and to condense the steam in the space i above the core. At the same time the system essentially con- t emergency injection; 3) flost controlled valves t 6) limitin g inserts. F) pumps for cooling the failed half of the reactors sists of two subsystems I0016n capacity each since failure 0
- 8) idem for non falled helf t 9) leedpumps ($ pumpels of the system of storage tanks means either that water is not G supplied by two storage tanks to the space above the core or '
- foi fast operating volves: 10 nonreturn valves. C by two tanks to the do ncoming section. On subdividing the I system into four tanks each $0% in capacity, in the case of a G I
burst of the connecting pipe and of failure of another tank I'
ll is advisable to esamine the reshsstion of demands made two nubsystems will remain in operation, each $01 in capacity.
True. two tanks connected either to the space above the core C on the structure of the ECS and on the processes of heat 9 removal in the core both within the scope of the limiting or to tlas downcoming acwt6on may fa6l, llowever, hursting approach and within the scope of the statistical probability of the connecting pipe results in less mer6ous consequences.
0 approach, f.et us esamine first of att the arrangements of From thu formal standpoint this version does not differ from b
the esisting ECS of water cooled reactore. Figs.1 and 2 the version of three subsystems 50% each in capacity with d
show the emergency cooling systems of the VVER 8000' and supply of water only into the downcoming sect 6on.
r -+w
+ '
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. Thermal Engineering. 30 G.1983 63 The situation may be even more terrn.s if we assume that the re'. tion between the characteristics of structural reliabil-with MCA one of the subsystems of the storage tanks is under ity as.d the ideality of cooling over the stage of operation of repair. and another is ineffective owing to a burst. This the tanks of the VVFR and RD\tX reactors, approach is adopted in west Germany'. The special feature The results of calculation for the subsystem of the ECS of the new emergency cooling systems of 1300 MW units in tanks of the VVER reactor have shown that the riost signifi-that country is the arrangement of each individual subsystem cant units in the system are the nonteturn valves installed of passive injection of two storage tanks connected to the hot two on each inne connecting the tanks to the reactor vessel and cold runs of the pipelines, instead of one storage tank ( Fig .1 ) . These valves are not inspected or tested for nearly in the prevsous arrangements. which tcads to the necessity a year (over the working campaign). Therefore, under con-of instalhng eight storage tanks. l!owever, such an approach daticns of lJck of statistical data on failures of these nonre*
to the securing of emergency coohng in the case of such turn valves we have so far to be guided by the worst of the improbable failure as MCA is hardly advisable, available data. The intensity of failures n of ordinary non.
For the ECS of the RBMK reactor redundancy of three suba return valves according to evallable data varies within limits systems $0% each in capacity has been chosen. and meter of 10**-10" IIh. It is interesting to note that at t = 10*'
supply to the channels is arranged only from below. Unlike 1/h the probability of trouble free operation Rg nf the system the ECSC of the VVLH reactor, a burst of one of the headers of tanks everaged over 8640 h is 0,999334, i.e. it meets the of the LCS will not tcad to serious consequences since the hmiting value 0.99399 derived on the b:nis of trf principle channeta of this half of the reactor will be cooled by the of equal rehabihtyl flowever. At k a 10 1/h R t is 0.9334.
reverse flow of cootant. and afterwards this header can be i.e. less than the above value. Thus, it is necessary to
, cut off from the appropriate group headers and cooling of the bring the retsability of nonreturn valves to the rcquired level channels can be fully effected by feedwater, in accordance or to install additional nonreturn valves in parauel with the with the single failure principle there is no need to increase esisting ones. At present the second way. which was the rate of redundancy of the ECS of the RD%tK reactor to recommended for practical use. seems to be the best, the level of the ECS of the VVER reactor. Anstysis of the significance of the equipment of the ECS The main subsystems of the ECS shown in Figs.1 and 2 of the RBhtk reactor has shown that the greatest influence on have e double and triple arrangement, depending on the its reliability is exerted by the gate valves and by the non-classification of failures of their equipment. Such an return valves (10.11 in Fig.21. In this case we can he approach makes it possible to guarantee supply of a certain guided by the reliability demands which are made on the amount of emergency coolant. which can be regarded as the system of tanks of the ECS of the VVElt reactor, although nominal amount. On the basis of such reasons only it is redundancy of equipment and conditions of maintenance are fairly difficult to develop optimal arrangements both of indi. different in them. The emergency conhng system consists of vedual subsystems and of emergency cooling systems as e two subsystems of tanks and of a subsystem receiving water whole. therefore it is advisable to supplement limiting esti. from the feedpumps which continue working duhng shutdown g males by statistical probability estimates, based on the con. of the turbine generators. It is assumed that the output of cepts of structural rehability. Bukrinskli' suggests e each subsystem amounts to 50% of the ratad finwrite. i.e. the princapk of equal reliabihty of ufety systems, on the basis structure of the system of instantaneous mjecteo is three of which one can determine the required quantitative charac. subsystems 50% each in capacity. In this case tre operation.el terestics of relsability of the systems in selection of the readiness Kl . which characterines the reliabshly of the given probability criterion of safety at e level of 10** t/ year, system (with allowance for the possibility of restering it To reahse the statistical probabihty approach. development without shutting down the reactor) is of the form:
of an appropriate method is required. The method of tree of ~ . "*
fastures" for analysis of structural reliability of safety sysa N' ~
tems is best known. For a number of years Moscow Power where Q, = operational nonreadiness of the EC5. Oss si institute has been developing different program etgerithms operational nonreadiness of the subsystems, based on the main propositions of this method"*" which With this approach. even with allowance for dupheating the have been used for the emergency cooling systems both of gate valves and nonreturn valves the value of Kt is lens thin the VVER and RDntK reactors". As a result of detailed study the one obtained on the basis of the principle of equal rein-of the evallable and predicted statistics of failure of main bility. One should bear in mind that the investigitinns of equipment of the safety system o spectrum of the main quen* the processes of heat removal have shown the feisibihty nf titative characteristics of ECS reliability was obtained and adequate coohng of fuel elements at flowrates less than rated these were compared with those required determined on the by a factor of 1.$=2. In that sase the actual structure of fusis of the principle of equel reliabihty. the emergency cooling system is three subsysteet 100t cach For safety systems the period of functioning of which is in capacity. and the formula for determination of N1 of nuch very short (these arrangements include the tank systems a system is of the formt Kg = I = Qss' both of the VVF.R and itBMK reactors), the determination of The structure of three subsystems each 100% in capacity probability of tripping within a certain time interval la more considerably improves reliability of the system with allowance essentiel in estimation of rehabihty. In this connection the for duplicating the gate volves and nonreturn valves.
. mein analysis of reuebility of the above subsystems is carried Nevertheless e value of Kt t 0.99999 can be obtained, if the out on the basis of everage probability of tripping or function intensity of failures of the gate valves is not greater than of readiness within a time intervat up to 8440 h. For other 10** t/h.
ECS subsysterns analysis wee also carried out alth allowance Analysis of the reliability of the pumps of the ECSC of the
- i for periods and duration of inspection, conditions of restoring VVER reactor and of the ECSR of the stD4tX reactor hat
, , equipment, and duretion of functioning, flowever. In deter- shown that with the esisting equipment one can attain gel a
mining the effectiveness of emergency cooling the most reliability on the basis of the principle of equal rehability.
essential per6od is the initial period of functioning of the ECS. If one choosee certain values of the per6od and time of inspec-1 during which the course of the temperature curves of the tion. Thus. for the pumpe of the cuoling system of the i
fuel element cens end. correspondingly, their integrity le failed half of the RBMK reactor the required period and time j determined . Therefore it is first of all necessary to establish of Inspection amount to 720 and 0 h.
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64 Thermal Engineering. 30 (2).1983 From the cateutations it follows that selection of redundancy of an alloy of tirconium with niobium. It was confirmed that of the main equipment on the sangle failure principle is on the the rate of wetting of tirconium alloy tubes is double that of whole justafsed, however the rehability of the subsystems can stainless steel tubes of the same site (at the same parametersh be considerably improved by comparatively cheap measures llowever, with allowance for the conservative nature of' cal-selected on the basis of the statistical probability approach, culations for securing safety of NP stations es well as due The technical ideality of emergency cooling is determined to the fact that data obtained on stainless-steel surfaces are by the processes of heat removal during the stage of water distinguished by higher stability, the main characteristics of supply to the channels of the core. Up to the present time heat transfer are given for the stainless steel tubes. In there have been no generally accepted approaches to calcula- order to attain greater approximation of the tubular channel gion of heat remowat under smlar condissons which is to the unit of an actual fuel assembly, we testes at the same esplained by the comptes nature of the thermohydraulic pro- thermohydraulic parameters tubes with inserts uf plates of cesses uceurring in this case, actual spacing clements. insta!!cd 250 mm spart. Fig.3 gives with supply of cold water to dry and heated fuel elements the time dependences of the heat transfer coefficient a in a wetting front is formed, which is normally termed a repeated the nonwetted tone, in a smooth tube. and in a tube with wetting f ront bec1use origintity the cans of the fuct elements inserts at the parameters characterising the worst conditions were wetted under conditions of rated conhng before the of emergency coohng of VVER reactors. The graphs show onset of MCA. The wetting front divides the channel into that heat transfer in a tube with inscris is appreciably better threc t ypical sones - s wet f u'8e. writing f ront . .ind nonwetted than in a smooth tube, tone. The m,un task is to calculate heat removal in the non- On the Nais of the experiments. theoretical dependences wetted tone, smcc it is in this tone that increase in tempera- were Aveloped for the main characteristics of the heat-ture of the can of the fuel element may take place after admis- remeval process under conditions of repeated wetting": heat sion of eniergency coolant into the channel. Evaluation of flum in the wetting front rate of wetting and heat transfer heat transfer in this tone is diffscult also because it is pos- coeffseient in the nonwetted tone. Detailed analysis of the sible to reproduce and to study this state under steady state esperimental data and comparison with foreign data have conditions only within a narrow range of specific mass flow- shown that the dependence for o from flef.20 gives to a rates &w and of mass steam contents x since heat transfer certain estent too low values of heat transfer coefficient.
In the nonwetted gone normally takes place at x considerably This can be emplained in particular by the fact that in pro-less inan Jcr at which ttic states of post critical heat trans- cessing esperimental data the dependence of a on well tem-for are reached under steady state conditions at the corre- perature T,. which represents the contribution of heet sponding parameters. transfer by radiation and at ATw w T, - T, 2 600 K can be f or a number of years Mowow Power Institute has carried apprectable under certain conditions, was not taken into out esperimental investig1tions into the prucesses of heat sem unt . To estimate heat transfer in the nonwetted none transfer under conditions of post critical heat transfer and we propose e simple relation of the form:
of repeated wetting in pipen both for the entire range of ,,,,,,4,,, 4,,,,, 2}
parameters of emergency cmbng of VVI:H reactors*" and for the typical modes of conhng of Itit\1h reators'*. It where str.b w heat transfer coefficient in the region of should be pointed out that an early as the beginning of the transient boshng in the tone of the wetting front. Wim' K:
' seventies the 1 Ll;CitT caperimental programme nf investigs- % s M0 00018m WI8 % h tion of the heat transfer proecsses under conditions of repeated wetting was carried opt in the USA on full scale p varies within the interval 0.1-0.5 MPa.100 K e AT, e fuel assemblies of water-moderated water-ecusled reactors with 400 K.
simulatorn of fuel elements. and recommendations were The heet transfer coeffic6ent in the nonwetted none under developed" which require very cumbersome calculations. conditions of heat transfer with dispersed slug end dis-The complexities associated with the procedure of carrying persed flows. typical for this sone et parameters p = (0.1-out esperiments in assembhes of fuel elements and with pro- 0.5) MPa. ow w (25-2$0) kg/m' a for sections remote from cessing of esperimental data have prevented development of the wetting front can be expressed in the form an neceptable model of the heat transfer prucesses under con- g. 9. .,
ditions of repeated wetting. S ubsequently, in vestigations were carried out on smooth tubes" on the basis of which liest transfer by radiation from the wall to the droplets of calculation models of the processes of heat removal under liquid con be calculated by the dependence taken from Ref.21 tunditions of repeated =ctterig mere developed. We should with true volumetric steam content of 0.99-0.995 and diame-nl o pomt out that 6n order le d: scribe esperimental data ter of droplete il-31
- 10" m.
obtained on the 1. TWT facetity use was mado of the latest cal- Formule (2) does not take into account the influence of the culation tode TN AC" to which for calculation of heat trans- spacing elemente. which lead to further increase in o which fer over the stage of repeated wetting use is made of depen- contributes to the margin in calculation of temperatures of dences developed on the basis of esperiments carried out in the fuel element cans. We should also point out that for-chsnnels of simple geometry. It is d6fficult to apply the mula (2) holds for conditions when, after supply of cooling results obtained to the fuel assembhes of Soviet VVgR reac* water, the channel le filled with steam / water mixture. The inr* since the equivalent hydraube diameter of the fuel period of filling of the entire channel with steamtwater mis-nsnembhos of Soviet and foreign water moderated water- ture with admission of water heated to Te (and it is this cooled reactors differs by e factor of at out I.S. In addition. state that is typical for the initial stage of filling the corel the spacer grids in Soviet water anderated water-cooled is 6-10 e. Over this period o increasen almost linearly frei reacturn are positioned 250 me apart and in the foreign a vetue slightly above sero to e value determined by III.
reacturs $00 mm apart. For the conditions of emergency cooling of the RD41K All this has led to the necessity of deteiled investigation reactor, which are characterised by pressure, specific mass of the heast transfer pruconses in channels of simple geometry velocities and heat inputs q higher than those in the VVER at the parameters typical of the VVER reactor. E s periment e reactor esperimental dets are lacking. The author and woru carried out both in etsinless steel tubes and in tuben Delysev" investigated heat transfer in tubes in relation to
Thermal Engineering. 30 RL 1983 65 sim6lar conditions. Fig.3 gives typical curves of variation in were used in the USA to substantiate the effectiveness of
- o. obtained at parameters corresponding to the worst con. emergency cooling of water moderated water cooled reactore ditions of emergency cooling of the RBMK reactor. Even et under htCA conditions. However, one must bear in mind cw = SCO kg/m's sufficiently high values of a are secured that the core of the 1, OFT reactor is only 0.6 m in diameter from the standpoint of ensuring reliable heat removal. and consists of 1300 fuel elements of standard power reactore Cherkashev et al.H report that on a model fuel assembly even shortened to 1.7 m. In the experiments the existence of two higher values of a were obtained, which were determined by peaks of temperatures of fuel element cans was confirmed:
the influence of the spacer grids, the installation of which the first peak at the stage of escape of coolant, and the led not only to turbulence of the flow but also to the forms. second after drying up of the core. It should be noted that t6on of additional wetting fronts. This was noted also in the sharp decrease in temperature after the first and second esperiments carried out by %f El on tubes with inserts, at the peaks could be due to the fact that the thermocouples were parameters of the VVER reactor. on the surface of the fuel element cens, and not inserted into the cans. Such Installation of thermocouples often leads to them cooling faster than the can.
Calculated curves 2 and 3 (Fig.4) were obtained using formula (2) and the emperimental data represented by curve a.m'm'K J in Fig.3. Since the emperimental data were obtained on ft+ -
stainless steel tubes and al cw tower than could be espected I M f
'f with water supply only from one tank the limiting tempere*
gj ture of the fuel element cans was not reached even under the worst cooling conditions, it must be pointed out that the
) second temperature peak on curves 2 and 3 is lower then that g l - -
] obtained on calculated curve 4."
g=-c
~
ro! L i e e i T. K
~~
0 1C0 N3 HQ eco , t.s s ~l T
- v \ .
lI Figure 3. Typ6est curves of variation in a with time at the f.*Jr f -
paramettre of emergency coohng of the VVER and RlutK reactors, obtained in steintess steel tubes, 1.2) smooth tube, g, L, l
.- M.-
h W}T Nl h 12
- 2 mm t ow = eff kg/m's. p = 7 MPat Tgn = $50 N; ;
I I \ l '
q = 360 kWim'; T'" = 973 K; as = l.4 m; es = 2.1 m ; -
gl ,;g - - --
J) smooth tube,10
- 1 mm. p = 0.1 MPa; q = 50 kW/mi #1 r #l ,~ --. ,
ow = 100 kg/m s. T(n6 . gt3.g g g3 g ; y{n = 370 K; 8
l e = 1.0f $ m; di tube with spacing elements at the same I g
parameters (cross section between spacer grids).
~
JJ b .W .W W r. s On the whole we can say that the values of a obtained in Figure 4. Temperatures of the cans of the hottest sections tubular channels etthough lower then in fuel assemblies are of fuel elemente of the VVER reactor under conditions of distinguished by greater reliability and therefore one can emergency coohng. l} caper 6 mental date of li)fT reactor rely on them to a greater entent et least in plotting theoreti* gq max 39.4 kWim b 2) calculated data for VVER 1000 can retellone. Esperimente carried out on full scale fuel ,g ,=g ,ggg a g p, g 7 g, assembhes must mainly be used for confirming the selected mal ,42 kW/m; ancepts of emergency cooling. dual
- 2) idem heat withrelease.
a taken according u according to curveto Ref.2; gig.*3; 4 in 4) cel.
On the beste of the investigat6one into the heet transfer culated date".
processes under conditions of repeated wetting of heating surfaces it become possible to study the temperature fields of fuel elemente of the VVER and RintN reactors el the stage of emergency coolant supply. Mth this end in view suitable program algorithms were developed"'". In which solut6cn Temperatures of cans of fuel elements of the RBhtK 1000 of the two dimensional equation of unsteady heat conduction reertor over the elege of drying and of cooling water supply by an esplic6t enethod under boundary conditions determined were also celeulated. The time for total drying out of the by assignment of the selected dependences for ele incor* channels is of great importance. This time is determined po ra te d . For the parameters of emergency cooling of the tsoth by the processes of evaporation of steamIwater misture VVER reactor, calculations were carried out under conditione in the channels and by transfer of water from channels of of water supply to the channels of the fuel essembly only greater power into channets of lower power". For the from beneath. Residual heat release was calculated by the channets of the RDMKal000 reactor of 3000 kW the time for relations adopted for the standard of the American Nuclear complete dryout een be estimated at about I s. Over this Society ( AN5) with a 20% deviation towards the higher olde". t6me temperature of the cane hardly vams. Then nearly Fig.4 gives temperatures of the fuel element cane of water- adiabatic warming up of the fuel elemente starte in the steam moderated water cooled reactore. calculated for different snedium . According to tests on the valves, the required flow heat transfer conditicos, and also shows the etenperleon with le ensured in t=3 e frore the instant of transmitting the pulse evallable calculated deta 8 and with the results of tests on the for opening". In the calculat6cne, times of interruption of 14FT reactor'. Esper6mente carried out on this reector cooling water supply of 3-5 e were adopted, and at the same
s 66 Thermal Engineering. 30(2).1983 time it was assumed with a certain margin that over the given VVER res: tors. We should point out that only the questions period a = 0. of thermotechnical reliability cf reactors under rated condi-To determine the hmiting conditions of heat removal one tions of steady cooling have been dealt with in detail'. In must know the variation in thermal power of the channels determination of the thermotechnical stability of fuel elements with Isme. Use was made of the two approaches adopted in of water-cooled reactors by the statistical probability method itefs.26 and 27. With use of the first approach one obtains a number of difficulties arise due to finding the distributions too high values of power due to the allowance made for the with time of the levels of heat transfer and of energy release 3 s delay of the signal for tripping of the emergency protec- in relation to the particular rated values. Therefore in one tion and the steam coefficient of reactivity. Eme!'yanoe et may or another one has to comtine the elements of the limiting al. give a more realistic variation in power of the channels and statistical probabihty approaches in calculation of thermo-with time. So much the more important to note that even with technical stability of fuel elements under conditions of emer-the energy distribution adopted in accordance with Bulkin gency cooling. liwever, as the procedures for calculation et al.. which can be regarded as the greatest deviation of thermohydraulic parameters, modes of heat transfer and towards the higher side, and at "a = $00 W/m' N. which was of energy release are improved, similar calculations will obtained as the minimal value in experaments on smooth tubes become as necessary as calculatio... of structural reliability at lower .w (down to $00 kg/m' n). maximum temperature of of the ECS.
the can remains appreciably lower than the hmatang level. In this connection. determination of the probability indes Thus, also in the case of the channel type reactor the of effectiveness Il) amounts to determination of the struc-requirement of tiie deter runastic approach is essentially met when, with all deviations from rated parameters towards the tural reliabahty of the ECS on the assumption that Ph* = 1.
Of course. in order to arrive at such a conclusion it was worse side the hmating temperature of the fuel element canning necessary carefully to analyse the modes of heat transfer and is not reached. With the use of the energy distribution the processes of energy release at the stage of cooling water adopted in flef 27 interruption of cooling water supply for up supply. At the same time one should bear in mind that the to S s is possible. The curves given in Fig.5 also show the limiting approach is justified so long as to high a limiting influence of heat transfer in the gas cicarance age on varia- temperature of the can (1475 N) is adopted. Once this tem-tion in temperature of the can. We can see that the influence perature is reduced to 1000 N. on reaching this temperature ofenge on Ten as compared with the coefficients of heat for a short time the cans of the fuel elements do not undergo transfer to the cooling medium o is not so appreciable, appreciable changes, as 6mmediately the necessity arises for probabilistic calculation of all possible deviations of parame-ters from the nominal values.
Thus, on the basis of comprehensive investigation of the structure of the pystems, processes of heat removal, and T. .. K 'T*
ta00 f "thermotechnical stability" of fuel elements the required effectiveness of the existing means of emergency cooling of tJ3 water-cooled reactors has been confirmed and recomtnenda-
., Y tions with regird to their further improvement given.
IVe -
'J 5 tt ItX -
1.13 IX -
yg ,
REFERENCES N*
t
- 1. V. A.Sidorenko et at. Atomnaya energlya 1977 (S)
JJJ 360-369.
- # # ## # U ' 2. New acceptance criteria for emergency core cooling trigure S. Temperatures of the cens of the hottest sections system of light water cooled nuclear power reactors, of fuel elements of the RD4N 1000 reactor under conditions adopted by Nuclear Safety Staff. Nuclear Safety, of emergency emhng. Variation in energy release for 1974 (2) 173-184, curves 3.J.3.8 according to Ref.26. for curves 3.d according 3. C .D.McPherson , liest and Stass Transfer lessons to lief.274 f ) a = 0.5 kW/m' N a e = 1kW/m'Ni learned from the LOTT programme. fical Transfer
- 2) o a 0.1 kW tm8 Ns a w 4kW/m N 3. 4) e = 0.5 Nuclear Reactor Safety seminar. Dubrovnik.1980 kW/m' N a o a 3)n m i kW/m' Ng o e= D' E 4 kW/m' N; N oI kW/m' =i kW/h N o Ns 1 kW/m' K a interrup, 4. The reliability of power engineering systems, tion in cooling water supply for cu!,ve=s f.f.4-8 le 3 s. for Terminology. Nauks.1980 (951.
curve J ft is 5 s. 5. A.I.Niemin et al. Thermohydraulle calculation and thermotechnical reliability of nuclear reactors.
A t omis dit . 1980. 261 pp.
- 4. A .M.Duk rinskis and V.P.Tatarnikov. Elektricheskie reum the data given in Figs.4 and 5 it follows that even s ta nt ali. 1970 (0) 5- 9.
under worse condations of heat removal the requirements of 7 V.P.Vasilevskii et al. Safety systems of NP stations the limiting indes of the effectivenese of emergency cooling with RB%tN 1000 reactors. Transactions of All Union I
Te n
- T c'n* a re m e t . Essentially. the given results sneen Scientific Research institute for Design and that we need not yet resort to the statistical probability E m plo rat ion . Design and scientific research in the estimation of temperatures of cans of fuel elements et the field of nuclear power engineering,1979, 4$-l$.
stage of emergency cooling, although the author et al.H co n- 8. A.M.Dukrtnskii and Yu.V.$hvytysev. Elek t richeskie ducted similar calculations in relat6on to the conditions of the stantsil.1941 (3) 12-16.
e 3' Themat Engineering. 30 (2),1983 67 g 9. F.Mayinger. Large scale tests and modelling aspects II. R.Seben et al. UC-B Reflood Program: Experimental fer LOCA analysis of PWR. Heat Transfer Nuclear data Report. EPRI NP-743.1973.
Feactor Safety Seminar. Dubrovnik. 1980. Sept .1-S. 19. T R A C-TI: An Advanced Best-Estimate Computer
.s 155-102. Program for PWR 14CA Analysis. NUREGICR-0063 g 10. h . E . Ve sely. A time dependent methodology for 1974 1.
s fault tree analysis evaluation. Nuclear Engineering 20. L.P.Kabanov et al. Empirical dependences for emain and Design. 1970 (2) 337-360, characteristics of the process of heat removal at the o
, 11. A . A.Boyadthiev and L.P.Kabanov. Algorithm for parameters of post-failure cooling of a VVER reactor.
ng calculation of reliability of complex power engineering Preprint. I AE 3171.1979.
- w. systems by the fault tree method. State fund of 21. Trans ASME series C. 1976 98 (3) 79-86.
. a'gorithms and programmes. All Union State Stand. 22. Yu.M.Cherkashev et al. Nuclear Power Stations.
a rd 25-33.1977. Edit, by L.M.Voronin. Energolgdet. 1981 23-32.
- 12. L.P.Kabanov et al. Nuclear power stations. Edit . 23. L.P.Kabanov and S.P.Nikonov. Trudy MEI.1900 by L.M.Voronin. Energoiadat. 1981 103-110. (474) 16-21.
- 13. L.P.Kabanov et al. Problems of safety of NP stations 24. A .M . B u k rin s kil. Emergency transient processes in a94 the aims of scientific investigations. A tomindat . NP stations with VVER reactors. Energolade t . 1982.
1979 23-27. 25. V.P.Spasskov et al. Voprosy stomnoi nauki i
- 14. V.Marinov and L.P.Kahanov. Teplocne r getik a . 1977 tekhniki. Scriya fisika i tekhnika yadernykh reak.
(7) 01-83. torov. 1981 (7) (20) 34-39.
l$. L.P.Kabanov et al. T rud y .\t El . 1981 ($30) 17- 25. 26. Yu M.Bulkin et al. Voprosy atomnot nauki i tekhniki.
- 16. L. P.Kabanov and S. A.Delyaev. Trudy MEl 1973 Seriya Reaktorostroenie. 1974 (2) (9) 3-9.
nd
,, (374) 92-93. 27. 1.Ya.Emel'yanov et al. Atomnaya energiya.1977
- 17. T.F.Cadek. D.P.Dominicis. H.Yeh, and R.ll.Lause. (6) 458-444.
Tw R PLECllT Final Report Supplement. W C A P-7931.
.. 1972.
O l'
r G
a e
53 in Fo ( h- S C -03F Gtt
Nuclear power A,..uc_ ear power in t 'le Soviet L-. .nion by B. A. Semenov*
Even though the Soviet Union is a large industrial five year period tlye construction of new fossil fuelled state which bases its economic development on its own plants in the European part of the Soviet Union will
- mineral fuel resources,it cannot afford to neglect the practica!!y cease, and by 1985 almost all increase of l development of nucicar power, because about 801 of installed capacity will be from nuclear power plants. The its energy resources are concentrated in eastern regions Soviet nuclear programme is based on two types of of the cuuntry. winfe 75% of the population and con. thermal power reactor
- the WWER pressurized light.
sumers of power are concentrated in the European part water moderated and cooled reactor;and the R13MK of the USSR. The transport of fuel from the east of the light water. cooled, graphite moderated, channel type Soviet Union to western regions constitutes about 40% reactor.
of the turnover of the country's rail freight.
Another important factor which led the Soviet Union The early years of the Soviet programme to favour nuclear power as a main source of energy was that nuclear power is less damaging to the environment The first nuclear power projects were started in the than conventional power. ',t Union even before the erid of the 1940s. In 1950 the decision was taken to construct the country's first By the end of 1982, the totalinstalled capacity of nuclear power plant at Obninsk, based on the so called nuclear power plants in the USSR exceeded 18 000 MW. channel type, uranium graphite design of reactor. The In 1981 the Soviet Union's nuclear power plants world's first nuc! car pcwer plant was commissioned on
{ generated 86 billion k%h electricity - 6.5% of the 27 June 1954. I cannot but mention that I had the country's total electricity production. During the next honour to work in the engineering and physics five year period the generation figure willincrease more laboratory, as well as in the operation, of this nuclear than threefold and will reach 220 billion kWh in 1985. power plant during the first five years ofits working life.
Since it is planned that the total electric power pro. The success of this nuclear power plant demonstrated duction in the country will be increased to about the great potential which nuclear power held for 1500 billion kWh, nuclear plants will account for 145 producing electricity.
of the total electricity production in the entire country by 1985 and for 24% in the European region. The USSR's plans to develop nuclear power could not rely upon only one type of nuclear power plant.
Althou& hthe capitalinvestment costs for nuclear This would not have ensured the necessary reliability and power plants are l} to 2 times higher than for plants stabuity. But at the same time, to develop any type of usinprganic fuel, the cost figures for electricity produc. nuclear power reactor up to a commercial scale requires tion in the European part of the country (including the time, and huge material and financial resources. To Urals) show that nuclear power plants see quite select the types of reactor which would be most comp titive. Thus the average cost of nuclear generated appropriate and economic for the Soviet Union, the electricity in 1979 was 0.793 copeck /k%h, whereas State Committee for the Utilization of Atomic Energy the average cost of electricity from conventional power set up a research and development programme on
! plants was 0.753 copeck /kWh. different types of nuclear power reactors: pressurized.
Of the 18 000 MWinsta!!ed nuclear capacity, about water and boiling water (vessel type) reactors, channel.
I 2.5 million kW were put into operation over the last sesen type boiling water reactors, organic moderated and l
cooled reactors, etc. In the course of this work some years from 1976 to 1982. The rate at which nuclear power is being introduced has nearly tripled in the types of power reactors were abandoned before they last five year period compared to the previous one. The reached the prototype stage. For instance,it became rate a which nuclear power plants are being introduced clear that in practice reactors with organic moderators is about 2.5 times higher than the rate ofintroduction and coolants are suitable only for small nuclear power of power plants using organic fuel. During the current plants. Work on this reactor. type resulted in the construction in 1963 of a multi. unit transportable nuclear power plant which had an electrical capacity of dr b Au p#Nnu ut n egy an 5 ft . arthl, 750 kW. The research and development on a number ei a personal mw by Str semenov, and H not an espreuinn or of thermal nuclear power reactor concepts resulted in 2-sp,e ornesat povoon enher of the IAL A or or the USSR. the construction of prototyge umts: the fitsi and second NMbM __
ONE ,,
3s Nucf2ar power -
y T:bfe 1. Main nucl:ar power plants in operation at end of 1982
. . Nerne Unis Gross electrical Reactor type Year of reaching power iM WI nominal power Novo Voroneth u 4 210 WWER 1964 41 365 WWER 1970
. HI 440 WWER 1972 IV 440 WWER 1973 V 1000 WWER 'j 1981 Setov ersk i 100 U Gr (Channel 8WRI 1967 11 200 hl U Gr tChannel BWRI 1969 til 600 F8R 1981 b)
Korsk I 440 WWER 1973 e il 440 WWER 1975 til 440 WWER 1982 Len.ngrad I 1 000 ROMK 1974 11 1 000 RBMK 1976 til 1 000 RBMK 1980 w IV 1 000 RBMK 1988 B, Arrnenian i 407.5 WWER 1979 @
13 407.5 WWER 1980 . be Kursk i 1000 ROMK 1977 N 11 1 000 R8MK 1979 Chernotsylsk i 1 000 RBMK 1981 sti 11 1 000 RBMK 1981 1 000 T:
c ill R8MK 1982 I th Rowne i 440 WWER 1981/82 en 11 440 WWER 1981/82 ge, enthno Ukrainshave P-I (South Ukreinel i 1 000 WWER 1981/82 th Sanoienstays i 1000 R8MK 1981/82 al ti;j Totas 26 17 370 Several ernell prototype, and districtAeating reactors (VK 50,80R40. SN 350, Belibia, etc.) with a total especity of some 900 MW have not treen included in this list.
I units of Novo Voroneth with pressurked water reactors; it was decided to base further development of nuclear the first and second units of Beloyarsk with channel- power on two thermal reactor types: the WWER l type reactors;and the Dimitrovograd boiling water Pressurized water reactor; and the RBMK, channel type reactor. uranium graphite boiling water reactor. The main nuclear power plants currently operating in the USSR are listed The USSR paid special attention to the development I
in Table 1.
of fast breeder reactors because, from the very beginning,it seemed evident that a large scale long term nuclear power programme could not be realized without The WWER reactee j fast breeder reactors. The first experimental reactor, with plutonium fuel, went into operation in 1955, The As already mentioned, the first two units of the capacities of experimental reactors which then fo!! owed Nov Voron*1h nuclear Pow't P ant l served as proto-have been successively increased. In 1969, a 12 MWe types for the standard serial reactor, WWER 440. These test prototype fast reactor with sodium coolant, BOR 60, prototype units were very reliable and had consistently
- went into operation in Dimitrovograd. high load factors
- averaging about 80%,sometimes
' even higher. In the course of development of the in the process of development, construction, and standard reactor, practically all the main components have j operation of different prototype units,it became c! car been upgraded and substantial changes made to the which types of nuclear power plants were optimal for design of the reactor as a result of the operating the specific conditions of the USSR. In the second half experience with the first two prototype units. The first l of the 1960s,on the basis of the accumulated esperience, I,'
two serial WWER 440 reactors were installed at Novo. No 48 IAE A SULLETIN, VOL.2$, No 2 gag
Nuc!:ar power N Voronerb (units lit and IVt Some small changes have been introduced into the design oflater units. At the Table 2. WWER reactors built, under construction, and planned up to 1990
(.
beginning of 1983, 27 WWLR. type power re.netors were m operation throughout the world, including thirteen Name Un.ts Power Remarks omts in IJulgaria. Cuchosluvakia, l' inland, the German M
- Democratic Republic, and llungary.
.i ,,, ,,,,,v, Total operating experience with the WWER.440 2 365 protoivpe reactors amounts to 115 reactor. years; maximum Neo Voronezh a 3 44o urlW
' "O "'
calendar duration of operation is 13 years. .These reactors ' '# "'
have a load-factor in the region of 0.75 to o.90, and their l **" "* **0 P ' * ' C'"d' '"'
base. load operation is highly reliable. The average annual load. factor of the WWER reactors is higher than that of ^'mcaian =2 407.s stitum i too m uism;c conventional power plants.
"8' "
Rovno s} ago Research and development work on the existing 3 i ooo
' %wER.440 reactors has resulted in the design of a much south ukra.nian as i ooo more powerful 1000 MW wwER, the first unit of which was put into operation at Novo Voronezh in 1980.
k"'" "* '"
Based on the experience of construction and operating zaporernskaya na i ooo the first WWER 1000 unit, some improvements have gn ,,,,;,,,,,, ,, , non been introduced into the design of the standard serial 1000 MW reactor.
Salakow ud i 000 The %wER reactors currently in operation, under con.
""nwa =2 1m struction,or planned up to the year 1990 are listed in Table 2. Together with the increase in unit power of Kuibi5h'v =3 1 000 the reactor,its range of utilization is also being Baskir =3 1000 extended: design and construction of %%ER.1000 3,,, ,, ,, ,
reactors in seismic regions have been started. It is planned to use the WWER reactors not only to regulate '.ir ce the efectrical output of the combined heat end power the frequency and power regimes in electrical grids but WER looo current'v under construction near Odessa will
- '"d*""'"*"*"""'"**'h**'*"'D*"d
also for the combined production of heat and heating this plant is not included in the table.
_ , electricity.
m
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. 6gYs nuclear giower station at .
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o
', . l' Nuct:ar pow:r On the basis cfits many react:r years cf cperating experience, the WWER is clearly capable of providing t reliabit and economical electrical power (Table 3). As
'b',
N' ~ < -
can be seen from the table, the capital cost of WWER.
type reactors has been decreasing during the first period N[ _ .u 6.,
~ ,
2 of their introduction and, for the third and fourth unit of Novo-Voronezh, reached the value of 200 roubles 3
%j]'
l per kW installed. The increase in capital cost of nuclear N.
4 g ' , power plants constructed later can be explained by g j ,
factors oflocal character, as well as by general trends 9
following upon the increase in the cost of production of m
p ;,d ; conventional fuel. Some of these units were constructed ri in the far North (Kolsk) and the Armenian nuclear p I power plant has been designed for seismic conditions
- f ]:.,;
r ,
and is, therefore, more expensive. Still it is worth 4 noting that the evolution in capital cost of Soviet f-i' s
- g. W,J[ ~
l J 3
h-g WWERs has no comparison with the increase of pressu-rized water reactorcostsin the West during the same fI 2,_i_, --
period. Thislatter,of course, was the result of a l u ] -
complex of other, sometimes not directly comparable
% h ng factors.
.Q ,
b' I g
gl [ ip li ,b The average cost of electricity produced by WWER 6-L , s: F nuclear power plants in 1981 is significantly lower than Iq 8
q that produced by conventicnal power plants. For q '
y d L : -
WWER nuclear power units with operating time of more
, 4 i ,
I i j than one year, the average load-factor is generally higher than its design value of 0.8.
~~4' i ~7 RBMK reactors The development of channel type light water cooled, graphite moderated reactors began with the commis-sioning of the first nuclear power plant in Obninsk in 1954.
A sectional view of the WWER 1000 reactor showing Thereafter the Siberian 600 MW nuclear power plant (1) upper block;(2) control rod drive gear;(3) control rod was put into operation, then, the first and second units svide sad Protectica ruba*:(4) ***ctor pressure vesset; of Beloyarsk with capacities of 100 and 200 MW, (5) reactor shaft:(6) reactor core (7) ducts for ionization chambers and their esbling. gP g, reactors in the USSR was the boiling water high power reactor RBMK 1000. The design of the RBMK channel l
l Table 3. Performance of WWER:
Po.we plant Unit instWied capacity Capital cost Electricity production Average load rector (MW) (roubte/kWl* 1977-81 1977-81
=--
110' kWh)
Novo.vorone th 1 210 326 7.4 0.63 11 365 256 13 9 0.87 Ill-IV 880 20o 30.1 0.81 l v 1000 308 6.0 11993-811 -
(oss k 1-II 880 263 31.0 0.80 Armenian 1 - 11 885 327 15 4 0 62 TotW 9 4 150 280 leveragel 103.8 0.78 feveragel Exchange rate of appron,matelv US St 3 to the routde.
50 I AE A Butt.ETIN. VOt. 25. No 2
- .e Nucl=r power
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- 6. Ooancomers
- 7. Ma.n circulation pumps (MCPI Je NN l
)
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- 8. Group despensing headers tGOHI 9 Water papehnes NN M h
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- 11. Upper biologecal shecid NN ; p 12. Laieral biolog cal shield a of
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- 14. coohng pond
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- 16. 8ndse crane s )
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'P I k n._ . c A sectional view of the RBMK.1000 renesor. With an eleetneat power of 1000 Mh. the reactor's thermal power is 3140 MW:
the cuotant flow is 37.5 K 10' t/h and steam capaaty $.4 s 10's h. The reactor entes mater semperature is 270*C and the
~
saturated steam temperature 284'C math a presure in she separator of 70 kg sm'. The omtut fuel enrichment is 1.81 ser resetor provides the possibility of obtaining Ingh power. e t here are eswntully no upper power hmits for channel-On-load refuelling ensures llesibility of the fuel eyde )pe reactors resultmg from fabrication. transportation l
and increases the avadabdity of the plant. and mostmg of the components.
e lhe design teature of harmg more than 1000 l hlany facters favourmg the channel type graphite-uranium boding-water reactors were taken mto mdn Jual prunai) aremts increases the safety of the collsitterJtitin ill tlie deVdopith ni and design uo:L isactor s> sisin a wriittis loss ot'coolarit ai;e:Jerit is
'llicy Were fnIIy conllrith'd duritig con $trHelioil Jfid pf Jt'lliJII) eiltlhhuhls' "Pd l i"" e ite.anw of the good ph sic.il 3 charJeten5 ties of the e lhe fahrteatioet of major 1(ll\lK ItXX1 components teactor ami the on load refuelling system. low enriched
- can bc iloue at esntmp nunntaetunng pl. mis. .m.! doe. tuel can he n ed with Ingh elliaency the dneharged fud not respn c the constna tion of new mdustrul enicipn c. lus a lon enuinuhle nutesul content; t.he burn up is Ingh.
~
u tlh piirgutw binll lJhess'atmg espnptnent anil the pliitoniuni ploilnes d m the fuel is utils/ed.
l _
. - - - - - . -. .- - . - ~. - - . . .-
.i sJ.,~.,
y + ' Nd I:ar power 4
Tatge 4. Operating results of R8MK 1000 reactors - ~ RBMK.1500 reactors will be 20 to 30'4 less than for RBMK.1000 reactors and thus will reduce the cost of N a te e Year InstaHed ' Electe. city t.oad- each kWh produced. .
capacity production factor 8" * ~*
4 Fast br'e eder reactors 1.en.e rad 18 2 4 -
In SPi te of the successful operation of two therma!
.iggt 4000 24.1- . 73.8 reactor types, the Soviet Union clearly recognizes that
- the solution so long term nuclear fuel problems for
,,,, ,,,, , , , g,
. ,co,o Lig8o 2000 13 89 79.g large scale nuclear power programmes requires wide 1981- 2000 13.54 77.3 use of breeder reactors. This is why the development 1979 2000 12.23 se.8 of breeder reactors has a special priority in the Soviet coere nyIsk 1980 2000 14.21 80.9 Union. And this is why, parallel with the development test 2 coo 13.44 7s.2 and introduction of thermal reactors, the fast reactors, 1
. BN 350 and BN 600. have been designed and commis-sioned.
Almost ten years have passed since the beginning of f~ After the first two RBMK.1000 units of the Power Operation at the BN 350 reactor. The reactor teningrad nuclear power station had teen commissioned Produces 700 MWth which provides for generation of (unit I in 1973, and unit II in 1975), the construction electricity equivalent to 121 MWe and for daily produc.
i-of a series of these 1000 MWe reactors was started. tion of 85 000 tonnes of distilled water. The BN-600 Durir.g the nine year period from December 1973 to reactor, unlike the BN.350, has an integral design and Decernber 1982 ten RBMK.1000 units, representing a m dule. type steam generators. The BN 600 started total capacity of 10000 MWe, were put into operation Power operation in April 1980 and in December 1981 in the USSR. (This includes a further two 1000 MW the reactor was brought up to nominal power of i- units at teningrad.) 1470 MWth. By I January 1982, the unit had produced 3.7 TWh of electricity after about 10000 hours of i
. The nuclear power plants are designed to have twin operation. Maximum burn up of fuel reached 7%.
i reacters;the two independent reactor systems having l
s nur .ber ofinterchangeable auxiliary systems. Such a The next generation of fast breeder reactors, BN-800 design has advantages in construction, operation, and and BN 1600, are being designed for serial commercial
.i maintenance. It makes it possible to start the construe. introduction. The designs of both reactors are based I tion and mounting of the components for both units on the experience and achievements of their pre.
almost simultaneously. The average construction time decessors, and have now been completed. The main per two 1000 MW units was 7.68 years, thus bringing design parameters of the BN 800 and BN 1600 reactors
', the average construction time of one unit to 3.84 years. are analogous except for the power rating. The increased electrical capacity of the BN 800 compared to 1 In 1980 the RBMK.1000 reactors produced the BN-600 has been achieved with approximately the I 47 bi!! ion kWh or 64.5% of all electrical power same capital cost, which represents the main factor in b (73 bi'u on kWh) produced by all nuclear po *er plants of the improved economics of the BN400 reactor.
- the consatry. The results of operation of RBMK reactors Significant economy is also achieved because i
during the last three years are presented in Table 4. components practically identical to those already As can be seen, the average load factor of these eight developed for the BN 600 facility are being used in the
, nuclear power plants is about 75%. This is of course an BN.800 reactor as well. The main design features of L outsta . ding result, not often quoted or recognized. the BN 1600 reactor are similar to those of BN 600 and The successful operation of RBMK.1000 reactors at BN 800 reactors.
nominal power and the reserves found in their design
[ (withcot changing the size and number of fuel Nuclear safety in the USSR l assemt!ies) have made it possible to increase the power
, of each process channel or fuel assembly by a factor The safety of nuclear power plants in the Soviet l of 1.5! Using only special heat transfer intensifiers, the Union is assured by a very wide spectrum of measures.
. total p wer of the reactor has been increased to the most important of which are:
! 1500 MW. At present the construction of the first Securing high quality manufacture and installation of l stage cf Ignalino nuclear power plant with two components; RBMK 1500 reactorsis under way. The commissioning Checking of components at all stages; l of the first unit will be the first step in the construction Development and realization of effective technical of a new generation of channel type reactors safety measures to prevent accidents. to compensate for which, since they will be more economical, should possible malfunctions, and to decrease ihe consequences i~
suceceJ the ROMK 1000 reactors. The capital cost of of imble accidents:
f 62 IA( A nUL LETsN. VOL 2$ Nu 2
=_ , _ _ _ _ _ _ _ _ _ ._.. _ _ _ _ ___ _ _ _._
Nuclear power
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Ihe omtrol e..im of she 1000 Stw l(intK Sm.Jenskaya nus-tcar power plant. .me of she ment rn nlern power seutoe in elic Sinwe L'ne..n.
I)eselopment and reali/ation of ways of locali/mg
- The State Committee on Supenision of Safe radioaeinity released in case of an accident. Operatmns m Indmir) and Alming under supeniston of iteati/ation of teelnneal and orgam/ational incasures the Counal of Almnters of clie t'Mit iGosgottellinailior to cinnre uret3 at all slages of s'onstrnetion an,I of the l'5 sit 1. ulu h supen nes complun.e with oper.itmn of nuclear pimer pl. inn. regulations anil stansl.irits of rn.emccrme safctr m deugn.
Itegulation of tc. inn (al and org.nniational asgwis m consernetion anil operation of nn.le.it p.mer plants sc.-m mg utch . and
- I I S i d ' v \ "' IC " S i l c h 3 "'l' ' h "' *' ""'"" J'I'"'
Intro lucten ol a ss sicm of state urch conisol
.init segn!.ition of the I %%I(I ulus h sugmnes t oinplun.e with rules -
and st. mil.n.ls of eme Icar sa/cti m ileu: n. 6 onst nec two.
t he segul.ilmn of ulch in .itti ul Jacumenh is .niil opciati. n ..I nii. l. .n lion es pl. ann one .it the m.nn f.els f oi rinunng the wich of nu leas p.m cs pl.enh in ths' I 5%I( l he state supen nh'n el e j he %I. ate %.sint.in linpc. f ron of the L %%l{ uiides nnsica, powei plant urch n . ...unptnhc l ln the \linnen .it l'ul'h. llcalih uln.h suren nes
', I
- Nuclear pow;r State Nuclear State Engineering Saf ety inspection M'n'sts y of Public Health Safety inspection State Sanitary inspection 1 8 1 i 8
I l l t , i l i l i e t 1 I I i General Safety Regulations l l 3
1 i
i iN i
t l !
Ra6ation Safety Design and @ ration i Nuclear Safety Rules Standards Rules Nclear satery regulatory bodies and documents in the USSR
{
compliance with rules and standards ofradiation safety The basic document in Cosatomnadzor's activity, in design, construction, and opetation of nuclear power Nuclear safety regulations for nuclear powerplants, plants. was introduced in 1975. It regulates nuclear safety, g verning n t rdy criticality problems in reactor The established system of three supervisory bodies Pendon, but also nfu&g, transportation and has largely determined the structure of the whole st nge Huel assembin It contahs the main c complex of regulatory documents on nuclear power technical and organizational requirements to ensure (
N*"I '* 'I* nuclear safety in the design, construction, and operation The main regulatory document on nuclear power of nuclest power plants, and the tr:Ining requirements plant safety in the USSR, Cencralregulations to ensure for personnel associated with reactor operation.
the safety of nuclear power plants in design, construe.
rion, and operation, was enforced in 1973. This in the field of radiation safety, the basic document document covers all types of commercial reactors by which the health and inspection protection bodies -
used and to be used in the USSR in the nearest future are gulded is Radiation safety standards /RSS 76).
(WWER, RBMK, BN, and district heating reactors). In These standards were worked out on the basis of this approach, requirements are presented in a general recommendations of the International Commission on way, without concrete details. In most cases the Radiological Protection (ICRP) and establish the 0 Centralregulations only prescribe tasks which have to system of dose limits and principles of their application.
be solved to ensure safety (what must be done)i they do The health regulations for design and operation of G
not determine the solutions (how it should be done). nuclear powr plants, issued in 1978, further develop and specify the basic RSS 76 document to include Other normative documents (codes, guides, rules,
- siting, monitoring, and inspection problems.
procedures) develop further and specify more concretely D the Generalregulations, establishing thus the basis for The system of regulatory documents on nuclear c activities of designers and corresponding supervisory power plant safety is complemented by the system of s bodies. One of the main documents in the field of state standards developed and established by the State i enginee ring safety is Regulations for design and safe Committee on Standards (Cosstandart of the USSR). I operation of components for nuclear power plants. The system of standards extends the system of a test aruf research reactors. andinstallations regulatory documents by ensuring nuclear plant safety B aar IAE A BULLETIN, VOL,2$, No ? I
y* I~
b =--- , -
Nucl:ar power
- through establishing requirements for many components. Fuel. fabrication technology in the USSR at the materials, processes, etc. present time has been developed to such a level that it can meet all the contemporary requirements for both
. The above documents play a significant role in the production scope and the required operational
! nuclear power plant quality assurance.
parameters of the fuel. .
. Stable, well proven technologies of fuel. element '
j Uranium exploration and mining manufacture together with correctly selected design
_ !.arge. scale development of nuclear power in the
' '" " * '"" ' *Y
- I
- c res f the nuclear power reactors nowin operation.
USSR is impossible without creation of a nuclear industry Fuel. pin failure resulting in the release of fission products using the most modern technology in all stages ofits into the coolant has become a very rare phenomenon and fuel cycle. The development of nuclear power and the
. . = the number of failed fuel rods is now less than 0.2J5.
nuclear m. dustry in the USSR would be imposs.blei with.
. To meet the increased scale of nuclear fuel fabrication, 4 out securing the raw material resources. In a rather short effective, automated production and control equipment period of time, uranium deposits have been discovered '!
, have had to be developed. In Soviet fuel fabrication
- in the country and a reliable resource-base established.
plants, welding and filling of the fuel tubes with pellets There are quite favourable prospects for its further is fully automated. Ultrasonic checks on weld quality, extension and increase. monitoring of fuel. rod integrity and of the rods' geo.
Uranium-ore deposits in the Soviet Union are located metrical parame ters, density, etc. are d highly mechanized.
In very different climatic and geographical zones, many The level of technology reached practically excludes fuel.
of them have complicated geological, hydrological, and element failures in the initial period of operation, when .
climatic conditions. They are found at different depths fabrication defects are particularly revealed.
from a few metres, to 2000 m and even deeper. The On the basis of the technological achievements in ore bodies are of very different shapes in different fuel fabrication, the fuefs operating parameters have
- locations and of varying mineralogical content. Com . been further upgraded. Thus the fuel for WWER.1000 mercial deposits of uranium in the Soviet Union are reactors was originally designed for a two year regime characterized by a wide variety of conditions of with a maximum burn up of 40 GW day / tonne of
,~ localization and of various generic types. At the uranium. The positive operating experience accumulated present time uranium mining represents a separate and with the reactor and investigations in research reactors important branch of the miningindustry. Depending have a!! owed the Soviet Union to start fabricating fuel on individual geological conditions of deposits and the elements designed for a three year cycle of operation,with content of uranium in the ore, the treatment of a burn.up of 55 GW day / tonne of uranium. Starting in
, uranium deposits is carried out by: underground 1983 the WWER.1000 reactors will operate on a three.
) mining; open pit mining; or in situ leaching. year cycle. The burn-up for RBMK. type reactors is lon-exchange technology has been very rapidly Pl anned to reach 25 to 30 GW day / tonne of uranium.
j develored for the uranium industry and is at present the basic industrial method of extracting uranium and Spent fuel management o , other elements from the ores and concentrates, from natural and mine. water, to obtain end. products of high From the very beginning, the Soviet Union planned purity. A method of uranium extraction from to close the nuclear fuel cycle, that is, to reprocess spent
. phosphoric acid solutions, which form in the process fuel and use the plutonium in fast reactors. Spent fuel
) of seid leaching of uranium. bearing phosphoride rocks, from nuclear power plants built in other countries with l has bec . successfully used in industrial scale operation the Soviet Union's assistance will be reprocessed in the
+
. In the Soviet Union for about 15 years. USSR, so in a sense the Soviet Union can be considered as a regional centre for nuclear fuel reprocessing.
! Enrichment and fuel fabrication Standard nuclear power plant designs for the WWER l
- reactors envisage storing spent fuel for a three year
- In the second half of the 1940s, industrial facilities for cooling period. However, because of delays in the serial 2
the production of uranium hexaGuoride and its subsequent construction of fast reactors, construction of additional, i enrichment were developed and built in the Soviet Union separately located spent. fuel stores designed for about i within a very short period of time. The technology of ten years of nuclear power plant operation is being i ; hexanuoride production developed in para!!el with that considered. This solution, however, does not remove the I- j of nuclear power and has reached now a high degree of need to transport and reprocess spent fuel, but just slows l sophistication. Developing methods and setting up down its implementation. Spent fuel from WWER.440
- e industrial plants for isotope separation of uranium by reactors is transported by train using four to eight gas diffusion presented extremely complicated scientiGc special container vans and two accompanying cars. For t and engineering problems. All these problems have fuel shipment from RUMK and WWER.1000 reactors t been successfully solved by the USSR. other types of railway containers are being developed.
9 I AF A nUL.L F YtN VOt. 25.No 7 55
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The nuclear-powered ice breaker ArkriAs. whid went into operation in 1974, leading s conwy of ships thsough northerr, waters When the problen of creating a Soviet nuc! car solutions are evaporated. After hardening, the residues industry arose in the 1940s, scientists at the Radium are sent for storage, while the wates can be used for Institute in I.eningrad developed the technology of technical purposes. The final volume of wastes to be .
plutonium extraction from irradiated fuel By 1950 the stored is only 0.2% of the initial one.
USSR already possessed the industrial technology to extract Pu-239 from irradiated natural uranium. In Medium level wstes are currently kept in stainless steel 1952 work started to perfect a method of reprocessing tanks (without cooling systems). For more reliable .(
the irradiated fuel which would be dir. charged from the and more economic storage, bituminization has been f first nuclear power phnt in Obninsk. After rnany years of developed and it is planned to introduce rotary work, scientists, technologists, and designers have bituminization devices with an output of 100. 200.and developed reprocessing technology for WWER and 1(BMK $00 t/h at nuc! car power stations. Bitumen blocks fuel eternents which separates and extracts uranium and with an activity of 10' to 10' Bq/L are being stored plutonium from fission products with a high degree experimentally in clay soils. The possibility of ofefficiency. vitrifying intermediate. activity waste is also being studied.
Waste management //igh level wste Vitrif; cation is considered to be the most promising rnethod of conditioning high level Proper management of radioactive wastes produced wastes. The process has been cenprehensively studied by nuclear power plants and fuel reprocessing facilities and resulted in the technological development of one-
[ is an important subject of the USSR programme of stage and Iwo stage verk )ns of a highly productive nuclear research and developnent. process of vitrification.
Lowlere/ wstes: A un; versa!!y applicable way of The vitrified products are put into 200 L cont.iiners purifying low levelliquid wastes has been developed and placed in vertical concrete pipes, cooied by air.
using a two stage lon exchange process. The ion exchsr:e The repository design ermges the possibility of resins are regenerated and repeatedly used, and tne withdrawing the solidified wastes and loading them into SG I AE A sutLt flN. VOL.25. No. 2
. ..+ ,
, Nuclur p:wIr
, transport casks. The tirne of residence of solidified wastes in a repository depends on their initial heat release. W2$tes with a specific heat release of P 5 X 10 W/m' require a six year retention. '],',7 The Ministry of Geology has carried out a complex 9-study of geological and hydrological conditions in many regions for existing and planned nuclear facilities. Ilow. P * *{- J-
- j"**.***********I'*-
ever, the results of all scientific and field studies do not i y et provide a final answer on the most suitable type of .
' M; "b'*"*' 'f",
rocks for waste disposal. Rock salt, clays, granite, I.'.* ?- , .3
.- gneiss, diabase, porphyrite, and similar rocks are under _ w.- 'G
', consideration.
Nuclear ice breakers
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When speaking of progress in the nuclear power field g'%,w- g q " Q ,
., in the USSR, one should certainly mention the creation of the nuclear powered ice breaker fleet. The explora.
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. tion of northem seas is of great significance for the -
1 country and the availability of nuclear powered ice. -M- * -
breakers has marked a new era in the exploration of the Arctic Sea routes, i
,7
-{
, ,pf; The first nuclear powered ice breaker in the world
- # ~
Lenin was constnieted in 1959 and celebrated its The first audear powered lee breaker in the Soviet fleet, and the twentieth anniversary of operation in the Arctic ice in rust in W =Md the M It was buut in im.
December 1979. The next ship in the series of nuclear.
powered ice breakers, the Arktika, went into operation in 1974, and in 1977 the ice breaker Sibir started work.
The latter two ships are equipped with a standard contribution of nuclear power to the fuel supply 75 000 horsepower nuclear power installation and their cannot exceed 10 to 15%. This means that nuclear technical specifications are better than those of the ice. Power, while substantially a!!cviating the fuel and breaker Lenin. The operating experience with nuclear. Power supply problems,is not yet able to solve them g powered ice breaken in periods oiprolonged navigation, radically. The solution of these problems is possible the unprecendented journeys of Arktika to the North only through substantial broadening of the sphere of Pole and of Sibir to transarctic huh latitudes, have utilization of nuclear power.
demonstrated conclusively that nuclear powered ice.
About 20% of organic fuel consumed in the USSR breakers can solve tasks which are beyond the possibilities is bumed for central heating. The main consumers of
,g of conventionalice breakers. The Soviet Union is also centralized heat are again located in the European part considering the use ornuclear powered lighter carrier ships of the country. Thus the extension of nuclear power to in Arctic regions.
l centralized heating is considered as one of the most important tasks in the solution of fuel and power nd Further perspectives problems.
First steps to solve these problems have already been As already mentioned, the Soviet Union considers made. Smce 1973 a nuclear heat and electricity nuclear power one of the most important energy pr duction plant has been operating in the far north.
lied' sources and a part of the long term solution to the
- '
- SR, in Chukotka region, supplying the problems of fuel and power supply. In 1981 the .
26th Party Congress decided that almost all growth of t wn f the diamond miners Bilibin with heat and electricity. Also since 1973 the BN.350 fast reactor has
?!ectricity production in the European part of the been successfully supplying the 100 000 inhabitants 3 country should be achieved by the construction of nuclear power and hydroelectrical plants. The decision of the a wn o ochenko with electricity and fresh
,I will significantly alleviate the problems of fuel and water. Cunently, wasidest frmn the Deloyank Lenin-power supply. But at the same time, since less than grad. Kursk, and Chernubylsk plants is being utilized 25% of the organic fuel resources consumed in the Studies show that heat can be supplied from nuclear j s USSR are used for electricity production and, since energy sources either by dual purpose nuclear heat and during the forthcoming five year period nuclear power electricity plants. or by using nucicar power plants only plants can pruvide base load consumers with electrical for heat supply nuclear boilers. Thermodynamically, to power only in the European part of the country, the dual-purpose pbnis are more efficient, but more e2 sata 8tst.LE TW v0L 25.Ko 2
<a _
', 1* N*ucl:ar p;wer
. complicated to build and operate. Extensive research it is rea!! zed, cf crurse, that the bread introduction and development, and design studies have shown of nuclear power into most power intensive branches of that nuc! car boilers are both suf6ciently powerful the country's economy requires a reliable and assured (300 to 500 Gcal/h) and safe sources of heat supply supply of nuclear (uel. This is why the development to be located near densely populated areas, thus and introduction of fast breeder reactors is considered a climinating expensive long distance district heating paramount task. One of the important tasks for the pipelines The first 500 MWth nuclear boiler plants nuc! car industry is, therefore, considered to be serial (AST 500) are being constructed in Corky and production of breeders.
Voroner.h and it is expected that many more such plants will be widely used in the future. Nuclear power Co operation within the CMEA planis supplying heat cost more to build than boiler in the field ornuclear power, the Soviet Union is plants operating with crganic fuel but, owing to the Co operating closely with the countries of the Committee cheapness of nuclear fuel, the cost of the heat produced should be approximately half that from organic fuel. of Mutual Economical Assistance (CMEA). The long term The construction of the first big dua! purpose nuclear programme of co operation in the fields of energy, fuel, and raw materials envisages technical co-operation in the power plant for both electricity and heat production construction and introduction of nuclear power plants in has started near Odessa. A %WER.1000 nuclear the CMEA countries. As the bssic reactor type for power reactor has been chosen as energy source, nuclear power developrnent in the CMEA countries, the Since more than 15% of organic fuel in the USSR %WER-440 standard reactor has been selected for the is consumed directly in industry - including chemistry, first stage, the WWER 1000 for the second. By 1990 metallurgy, etc. - the introduction of high-temperature the CMEA member countries (excluding the USSR) plan reactors for industrial heat production as well as to to build nuclear power plants with a totalinstalled make synthetic fuel is being considered as another capacity of approximately 37 000 MW. An international pouibility of widening the field of applicability of commercial organization, Interatomenergo, has been nuclear power and thus ecoriomizing conventional fuel founded for the co-operative manufacture and supply of resources. Research and development in this field equipm'ent for nuclear power plants by the member is also under way, countries of the CMEA. Yugoslavia is also taking part 3
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Layout of the AST 500 nuclear district-heating plant, showing (I) the reactor;(2) primary-circuit by pass purification ,
system;(3) boron solution injection system;(4) intermediate circuit pressurizer;(5) heat exchanger to heating network; l l (6) emergency cooling system tank:(7) hest consumers !
l I i I 58 ~ 6 AE A BULLETIN. VOL.25, No. 2
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- Nuclear power 8'
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l l
1 tet erm g _,
l, De turbine hall of
~~~
he the saibin nuclear
~ '
, in l Po*'t P ant which supplies a diamond-h.**" N -
snining town in the Otukotka region e in the ran north.
) east of the (JSSR. ,
an in these activities. Up to now four WWER-440 power ,
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reactors are operating in the German Democratic Repubh,e,
'I four in Bulgaria,Iwo in Czechoslovakia. Hungary has recently commissioned its first unit, Poland and Cuba 6
[h uai have started construction. The totalinstalled nuclear i IIN power capacity in the CMEA countries, including USSR, N -
'l will reach approximately 100 000 to 120 000 MW d ,
by 1990.
I believe that both the results achieved and the plans ,
for further nuclear power development in the USSR and other CMEA countries are impressive, particularly in g the light of the well-known difficulties and problems 4 ; d '
i
..T that many other countries have had. I believe also that -- . .
the successful realization of the USSR's and other CMEA countries' plans for expansion of the nuclear power ,
sector will contribute substantially to the development p i i y
1 of nuclear power throughout the world. k ;eh ,
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Q Feelrod A sectional view of the AST 500 d'isuice-heating reactor, showing (1) core; (2) heat exchanger; (3),(4) lower and upper part of the reactor vessel; (5) reactor roof; (6) control rod drives; (7),(8) lower and upper parts of reactor shell; (9) shaft of draft sector of natural circulation circuit.
p.m -sG-3w arr2.#2. 59 e,2 lAE A BULLETIN.VOL 75.No. 2
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.p FI;EL E LE MENTS OF THE R BMK-1000 REACTOR V .~ G . A d e n . Y u . K . Biblia sh v111 .
A . S. Zalmoysk11. V. V. Kalishnikov.
V. A. Nikolaev A. V. Nikullas.
V. 1. Solyanyl. V. N. Filippov.
V. S. Ya mnikov. V. lV. Goncha rov, and K. P.-Dubrovia The constructica of the RBMK-1000 power reactorwitb anelectricalcapacity of 1000 MW is a new stage in te dev:lopment of channel uranium graphite reactors cooled with ordinary water. N experience butit up la plazaing and operation has enabled a reactor to be developed which at present is one of the principal types of reactors chosen for nuclear power stations (NPS) under construction; in the hture,it will produce a sipificant fraction of the electric power la the European part of the Soviet Union. The principal feature of channel sys-tema has been exploited in the RBMK-1000 - the capability of fuel recharging during operation, which permits the N!Mi load factor to be lacreased and the nonproductivo losses in the absorbers of the control and safety ot-m to he reduced.
Dealga of the Fuel Assembly and het Element. 'Ibe height of the active some of the RBMK-1000 (7 m) stipulates the special feature of a fuel cassette (Fig.1). which comprises two fuel assemblies disposed along the height of the cheanel, mounted on a central rod la such a way that the gap whid is necessary to compen-sete the extension of the fuel elements durlag operation is located at the oester of the active same. On the pntr:t rod are mounted the locating units of the cassette - the tall piece and noceplace. The upper sad lower t emblies are identical and ocasist of 18 heel elements each with an activo-part length of 3.5 m [1,21. The bel
( .ta la the assembly are spaced with ten grids of the cellular type. made of stalaless steel (Fig. 2).
la the RBMK-1000 fuel element, the material of the cladding and the ends of the units is an alloy of air-eentum with 1% niobium in the recrystallised state (Fig. 3). The diameter of the fuel element cladding is 13.6 mm, and the mialmem thickness is 0.825 mm. Pellets of habed uranium dioside are used as the Anel - they s have o height close to their diameter. In order to aa=Ta===te for the thermal expansion of the fuel aalumn.
thera are sphericallunes at the ends of the pellets. 'Ibe average mass of the fuel column is 3890 g sad the
, maalmum density is 10.3 g/cas,
( The diametrical gap between the fuel and the cladding varies from 0.18 to 0.38 ans. The the1 columa ~
is fixed by a helical spring during technical servlelag. transportation.and operation. In order to reduce the l pressure of the gaseous fisslam products (GFP) released abaring operation, a gas , collector is provided in the structure. The average statistloal ratio of the free vehtsee under the Snel element cladding to the volume of te loaded fuel during manufacture is 0.00. The lattial anodium under the oladding is helham at 1 kgf/cm8 .
1be pelacipal thermophysical parameters of the fuel sesembly sad fuel elements of the RBMK-1000 are given
, halow(11: . .
} Ma=l=uma operating power of mannel kw . . . . . . . . . . . . . . . 3000 Coolaat pressure, kgf/caa8 st ialet . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 80 -
st outlet . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 73 Coolset tesaperature. 'C:
et inlet . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 205 staatlet...............,..................... 284 Ma=Imum steam o0atent, abses I . . . . . . . . . . . . . . . . . . . . . 27 Mabimum velocity of steam
- water alixture, m/see . . . . . . . . . 20 C Coolant feed through worklag chamael at inm=Imuna power. kg/h 21,200 i Ma=imum thersaal flux from surface of feet element. W/csas,,, g3
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moseptooe 31 het de-sneat seseambly 4) tall i piese: 4 amt e pen.
l u==i=== tineer thermal power, w/om. . . . . . . . . . . . . . . ast Maahaum 9 met temperature. 'C. . . . . . . . . . . . . . . . . . . 1,800 -
j Average fuel barney, MW.dayshoa U . . . . . . . . . . . . . . 19,500 i Duration of operation of fuel elemment at ma=l==I power, days 1,190 Fuel Element Manuf acturlag Technology _ -
g Preparation of Fuel Cores. W fuel pellets are manutsotated by a cold-presslag method with suboe- .
aguest staterlag. The particle size of the starting powder of ursalum dicalde sineents to 0.4 to 0.0 p. 'De .
betdt for presslag is prepared la the following ways into the startlag powder la introsbood an orgaaio blading beasd on as aqueous 7-6 soluttaa of polyvigt aloobot. The mese htw is somspressed at a constaat
. pressure, ground, and screened through a vibrating sieve. *nen the -- m powder is dried off and f
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Fig. 2. Section of a fue1 element assembly:
- 1) spocing grid; 2) fuel element.
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Fig. 3. Structure of fuel elesment: 1) dead piece: 2) feel peuet 3) cladding: 4) spring: 5) sleeves 4) aosepleos.
pressed. 'Ibe pressed briquets are dried, and then statored la a water-contalalag a8=aarhare. Pouets with ,.
cs cacessive diameter are ground, h abeemos of surfsos cracks and chips la checked by a standard. Sultable 8
peHets satisfy the fouowlag conditions: deastty m10.3 g/cm external diameter 11.52 mas cuygen factor 2.00-e 2.02: fluorise and moisture content s 0.006 and s0.002 mass 5. respectively.
t Proporstlos of Fuel Element. N fuel pouets are toeded lato the cladding from the welded lower deed piece. In order to hermeticauy seat the lhel element, s isteeve is welded to the stadding with an opening through which the fuel element is eveausted sad fuled with helium. 'Ibe opening is them argon-are welded, the fuel ele-mest is tested for leak-proofing,and the nosopiees is welded to to sleeve. -
AH esens, except to weld of the sleeve opealag, are jotaed by electron-beam welding. In order to la-oreese the corrosion reelstance, the welded seems are a===alad
'Ibe outside surfsos of the thet element is subjected to pleiding and outselsving. The flaished feel element is tested for leak-prooflag by means of a battua leak detector at a temperature of 360'C.
Exportmental Investigations of the Effielesey of a Fsol Element i
In order to verify the striolency of a feet assemldy and of a fuel element, a comples of tests was under-l taken under ex-reactor and reactor conditions, lactudlag thermophysical and endurance tests of the fuel chan-7 end anodels of the assembly om special test rigs, and also loop reactor tests of experimental and normal '
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.ssemblies [3-5). .
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t O TABLE 1. Test Conditions of Experimental Assembitos
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2 18 PVTs l a-a 7 Mt Sc 8,5 15.2 Ces ensansas less taak pesof 3 12 PV 7t.12--4 31130 M,9 bl.2 3 elsenssa less Isak pse'ef 4 Il PVTs l 2-4 9 330 000 15.0 24,8 Asesambly Isak pseef
& 11 DVTs21-7 19 701 s00 18.8 25.7 The sante 8 17 s.l l-8 25eis $nn 34,8 48,8 Assenetty sopsessuelsed .
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TABLE 2. Maximum Thicknesses of Omide Films and Hydrogen Content in irradiated Claddings ess. k yea U 1 3 M3 4.8 3 g,ing 2 1 Set 15.2 30 0,ine i 3 SelJe kl.2 m o UDE Test-Rig Endurance Tests. The vibration stability of the fuel assembly was lavestigated on a steam
,, test rig, equipped with 12 thermoresistant tensoresistors in the fuel elesments. The coolant feed was varied from 5 to 34 tonaht, and the steaan content from 0 to 48 mass %
x._ During every 1000 h of testing (~60 10 8cycles) the fuel assembly and its abammel were thoroughly la-
Lad. h channel tube and the fuel elenients after the first 1000 h of testing had no traces of work hardes-lag or wear. The strconium surfaces were covered with a smooth (11al of dark gray color. With further test-ing, the state of the surfaces of the channel and fuel elements remataed ==Aa= Tad At the potats of contact of the steel separating grids with the channel tube and the' fuel elements, no traces of weer were observed right up to the end of the tests under steady-state conditions. As a result'of prolonged (~ 9000 h) tests, the conclu-sion was C r.wn that vibration of the channel elements and fuel assemblias under aa=d868a== close to worklag culitions is not dangerous.
l The design safety factor with respect to critica1 power for the feel assemMies of the RBhtK-1000 reseter
! - amounts to 1.38 during operation of the reactor i the established cycle of contiamous reciterging. Actual values of the critical power of the Anel assemMt.as prete obtained by empeniments on half-scale electrically L
bested mockups of a fuel assembly over a wide reage of coolant pressure, feed, and steam content, and it was found that with these same water flow rates these values enceed the design vehnes by 7-ItFL for " fresh
- heel
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asseenbiles and by 15-2tfL for spent fuel assembhos.
Experiments on electricauy bested l==dtaa show that se emergency la enoung with the steam minhare l 1eeds to a relatively sman (withis gee'11mits of a few tens of degrees) incrosse la feel element stadding tem-l perature. In this case, the fuel element claddings of zirconium alloys maintala their officiemey for a long tiaw.
Reactor Tests. Teste of the RB&tK-1000 thet olennents was started la 1967 [6, 7). Half-scale assem-Wies of regular design and shortened assembtles with a length of 1 sa were tested. In order to approainste - j la test conditions with abortened essembtles - the operating conditions of the regnier Anet elements, special channels were constructed in which the coolant cooled two or three test assemblies in succeselon. ' linus, the l cffective length of the tent fuel elements in Undise caperiments was increasevi artificially lay a factor of two or
- 7. .
three.
'line test data of seven experimental assembtles (Table 1) confirm the high efficiency of the RBMK-1000 ;
fuel elements with claddings of an suoy of strconium + 17e niobium. It can be seen from Table 1 that au the experimental assemblies considered were tested at maalmum 11asar power of the RBitK-1000 feel elements of
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- TABLE 3. Mechanical Properties of Clad. '
. h. dings, before and after 1rradiation at a Dif-forent Test Temperature .
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3 # IN II I? ##-1433 - 31 the I.antagrad nuclear power statloa. Despite the rigorous test conditions, la four of the seven assemblies a y deep fuel burnup was achieved which significantly exceeded the desip burnup. The average fuel burnup is as-O semblies Nos.3 and 4-8 amounted to (25-35p lesand the naart=um burnup was (43-40)* 10s NW.daysAon U laverage fuel buraup in the Immingrad NPS is 19.5 108 sad the panvi===i is 23.5 10 8MW days / ton U).
Assembtles Nos.3, e and 7 we're depressurised after adievlag a deep fuel burnup. As lavestigation of l
th2 fuel etenients of assembly No.3, la which the maximum fuel burnup amounted to 50.2 108 MW.daysAca U, showed that depressurisation was caused by a lack of free componestion space inside the fuel elements, and a L
lack of axial compensation gap la the assembly. In consequence of the high pressure of the gaseous fission products inalde the fuel elements of assembly No.3, the diameter of the stadding was increased maximally by 5'.< la addition, there was no axial compensation gup in the assembly, amounting to 1.5 to 2.5 mm la the initial state. The fuel elements rested splast the end grids and were beat. As a result of these deforsaations, through cracks were formed la the Anet element etaddings in the region of the welded seams. Because of tble, in the doelp of the regular cassettes, the asial compensation gap and the volume of the gas couector were la-xased, which wul la the future ==d=ta simuar occurroness.
.f-i .4. . . ' . Assembly No.2 was tested up to a ===8-an= fuel burnup of 15* 10s MW.doya/ ton U with a llaear power 9 C of 500 W/cm. '11:e power then was lacrossed to 750 W/ca, and after a certala time the assembly was takec out of servies. It was found that la the contral part of the cladding of the most stressed fuet eleinent of the ,
assembly a longitudinal crack had forsned.
E During operation la boding coolset, the hiet element eladdlags are enddised with the formation of a ace-uniform aside flim and they are very slightly hyd.:;:-ri It osa be seen from Table 3 that, even after i irradiation of the fuel element up to a very deep fuel burnup, onddstion and hydresseation "
do not limit the efft-elency of the fuel element claddings. The hydrides la the daallaga have a p. :" ' - annular orleatation.
In the region of the spacing grida (etalaless stoet), ao sooelerated corroelos of the staddinge of stronatum + 1% -
alobium alloy was observed. Also, timore was no unerked cladding erosion at points of sentact of the lhel elements with the spacing grids. ,
The taasue strength, yield point, and total relative linear espaaslam (Fable 3) were determined by trame- l verse tematon of amandar semples out out of he staddings. It oss be seen from Table 3 tot changes of sneeb-esical properties reed seenrotion after a relatively short irradiation time. The meseksalost properties of the Aset element alaatinga of assembtles Nos.1 and 3 are alsnoet identient. 1he hida relative linear expansion of
% the treediated daeunga (10-144 is important for sesommodating possible loost deforsnettone ceased by meeb.- ,
sa4 cat seteractimi af the fuel with the claddlag.
In the investigations, he almestity of gaseous fission proshnots released under the coollag of the experi-mental feet elemente sharing testing was determalmed after irradiaties. It was famed that the relative ytend of seasons fiestos prednota depende on the ==w8-= 11meer power et whid te feel elements were irradiated, but la -a y.-a e g the o feel buramp. In teet elements irradiated at a ===i=== linear power of 300 W/ema and lees, there is alunost no dis &arge of gas, last la fuel elesments irradiated at 700 W/ema, it amounts to 5dk The lavestigation of the linear espaaston of time fuel elements sharing power spellag was undertabes la a q sp faculty on half-scale assemblies with the fouowlag single-cycle conditions: lacrease of power from 0 to over 1.5 to 2 h hold for 40-45 ha reduos power from 100 to 45 over 1.Sto 2 h and hold at sore power for a me e
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In addition, tests were conducted during cycles with a long (2 to 3 days a ul more) holding at zero power, and also rapid power fluctuations, simulating the conditions during'lasertion of the scram rods. .
Cooling of the circuit during the tests was carried out with both a high rate achieving 3400'CA at the initial instant and with a rate not onceeding 180*CA.
Figure 4 shows the preliminary results of saessurements of the length of the heel elements, from which it follows that with burnups in excess of (3-5).10 htW.daysAon 11 a slow growth of te feel elements occurs dur-ing power cycling.
Thus, the complex of experimental, computational, and technologicalinvestigations has enabled a re-j liable design to be established for the fuel elements and fuel assemblies for a power-generating uranium-(-% _.- graphite resctor of the channel type, with an electrical capacity of 1000 n!W. .
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POWER DISTRIBUTION MONITOT.'INO AND CONTROL
- f FOR A RBMK REACTOR h '
I. Ya. Em el'yanov, V. V. Post alkov. -
and Yu. I. Volod'ko .
i .
De RBMK reactorshavelavolvedvarious difneelt problems is control of oore processes. partid'ulart la the mootterlag and control of the power distreutlos. Reliable powerglistribution control for reactors of this type is complicated by various factore: the high ask power and large size of the reactor, the xenon In-4 stability occurtlag la such remotors, the large amanber of monnoring potats and control devices, which con-
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i stltute a considerable lord of the operator, the complicated alerostructure of the power distribution. which la due to the large number of adduloaal absorbers la the lattial working period, and to b large nuaibers o adjacent fresh and partly worn out fuel-pla assemblies la the steady-state, la addittaa to b spatial lastabt due to the voki, temperature, and other remotivity ooefReients (1), and h comptenity la mostoring the pow
- distribution by heat-engineertag methods in casanels with a boilleg oootaat, 1
Some of these factors become more important to the structure of the oostrol syistem for a reactor of i
type as the size and unit power increase or as the specifloations for adammesa control are tightened.
i '
i Th's moottoring and control system for the RBMK-1000 laeludes three beste systems each having higt ladependent operations the control and proteottoa systess cps, the system for physteal snositortag of the po distribution CPMPD and the Skala oestralised monRortag systeam CMS. We ocasider the amata functions anc features of each system, with partleular attention to the movet featsres of the structure and movel features e a
h struc.ure and movel items of equipeneet. i o
De cpg [2] operates froas lateral loaisattoa ehmebers LIC. ha the aggraded form, the cpg is supple sneated with local automatie control LAC sabeysteams and local emergency protection LEP systemis, in whis triaxial fisslos chambers are used as the detooters [3].
The cpg la based to a oortata entent om destgas tradillosal for large arealem graphRe remotors and
- < provides for maattoring of the power and remeter perted together wtth ada==*e= malatemance of the reactot power la the reage 0.1-100% as well as adomatie essergeney pretootton if the power levet or rate of pores <
>! lacrease eseeed set limits, adosaatte essergency reestor protection froan deviatlass la h power distributt t
l at the periphery of the core correspondtag to the Arst radial-esinathat harunoales, montortag of the rotatt )
power distribdios at the pertphery of the remotor, and usament control of the positsens of the absorbing rode '
He lateral lonisation chambers are placed la the reflooter (fear shamberal and behted the renector (24 chambers), while hre are 42 chambers withis the resetor, whose positions are shows la the figure. T dfaa*ars la the control and proteotloa system are absorbing rods of three types, which are pleeed in.179 special stroostem channels and are oooted by water, knotedtag the.=mamman esattet rods MC, whlen number 1 i
the automatie control rods AC for the average remotor power, whtok number 12, and the short absorbing res i SAR, which numsber St. Fifty-seven rods la time manual control systems are used as emnergemey-protection #
and are withdraws fross the core during operaties. The height distreetles of the power is sentrolled by wit drawtag the MC and AC rods upwards, while the SAR rede, which have abee 6 tag parts of half the length, an i withdrawa downward.s. . .
De LAC system is designed for automatte control of reestor power and to staldlise the power distrit ties (4). When the remotor works with LAC, one of the AC must be la the het backup state. Switching from to AC or vice versa is performed manually, or ==*a-a*ea=81y, by means of the sevet effector orgsas for the LAC, which are analogous to the MC affectore, and b 42 LAC and LEP ahambers are malforunly distrede over the oore (Fig.1). Each LAC red is sorrounded by two LEP shassbers and fear LAC ehambers. He ;
averaged corrested signal fross the foer LAC chanabers is need to oestret the red. ' i Se SPMPD constats of two ladopendent odoystemas for mestiertag the power distribution ever the radius (BPMPDR) and the height (gPMPDif). Both systesse work froaa the laternal detectors ID that soonRo'
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Fig.1. IAcettom of the control rods and nominatton chaanbers of the CPS and of the '
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, SPMPD detectors la the RBMK-1000: 1) DMElt: 2) chaenet for estibraties y obamberg
- 3) detector for the LAC and LEP systeens 4) LAC and LEP redes El AC rod 4) MC i rods 7) emnergency-pretootles rods 8) short abeostdag rods 9) DMEII: 101 fisslos chamber: l'
- 11) lateral Santention obamber (outside a renactor). ,
the radial power distribelos DMER and the height distribdies DMEN, which provide preprocesalag of the signals, transmission to the computer, cossparison of the signals with gives levels, and generstles of saldable and visible signals if the detector signals go outside set llantta. He SPMPDR reestyes the signals freen 130 '
DMER aba= hare placed la the inset-pla assemblies, while the SPMPDit receives signale frean 84 DMEN ahambers placed at sevet potats steeg the height la la of the DetEH obammels. *
. De amanber and loestlos of the ID were ehesen en the basis that the perantestete power is a inset-pla assamably shoald caly be slightly dependent on the power distributies over the height of a chaamel Me to axial nonastformity coedeleients of 1.Y-2.00 and se deteransed la the sista by the new rate w pressure, and tempers-tare of the water at the talet to the pia assembly. H erefore5 the sPMPDR provides the beste latesual nonner-lag la the RBMK-1000s the DMERI chambere are latended la the anais for sneasterlag the stability of the height distribdies and to prevent eseessive linear lead en the heet-pla acessablies la asemalene attentlene. He samber and dispoonies of the Destif ah==ha=e are deteranimed by the regaired maatterlag and sentrol assersey.
De mesa-egaare error la diserete uneastentag of $ set-pla power at the smaximam distanes fWem the DMER ehambero is about S for the pIIek ehesen for the DMER lattlet, whleh is meek less than the erroes required ,
le prednee as apprestable deterteraties In the deteransestion of the margia dWeen the arttleal power la the Anot-red aseeenbty. Hereform, the DMER lattlee has soone redmedamoy as regasde the assessary unsalterlag ae-
. enracy. De deelga is alas latended to preteet the feel-pla assemblies trean erremeses entreetles of any la-i dividual adonnette-eestrol red, where eneh control rod should be operated with at least one laternal detester.
Here are seven DMEH ah==ha s malformaly Katributed over the height beonese of the spoetAcation for meester-lag the Aret four asial haranossos even when two detectors la one chamael fall.
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fo;;t-pin assembly, each of whith is cf the samo destgas a deter chambet consists of a sensitive element filled with crgoa la o cealed body of corrosion-resistant steel togeth:r with a sealed high-temperattre socket and a coupilag lia:. He maximum wtrking temperettre of the ceasing element la the DMER system is 350T:
ca emts:lon d-tector with a silver emitter is used. This detector is a radiation-resistant and heat-resistant I
coaxial cable made by a normal manufacturing technique used for h'igh-temperature cables with mineral la-sulatloc. *
- During the design of the SPt.WD for the RBMK-1000, the choice of sensing element for the power-distribe-
}\
tion monitors was essentially restricted to emisalon detectors with emitters composed of rhodium and silver.
Such detectors with silver emitters are rather faster la response [5}, which is due to b shorter half-life of the silver radioisotopes, as well as to more favorable p-particle energy, which means that there is only a 13%
j contribution or less to the detector current from the composeat.wlth half-!!fe of 2.4 mia, while there is prac-tically no contributton from the component with half-life 259 days. Also, a silver endtter has a lower rate of
! bura-up (19% per year as agatast 34% per year for rhodium for a sedron flux deastty of 1088 neutroas/cat .
see), together with a much lower dependence of the sensitivity on the neutros gas teenperature. Further, a cable with a silver core is easier to manufacture and more reliable, which is autremely importad for rodine production and operation.
De working !!fe of the DMER la not less than b worklag life of a fuel-pla assembly (3-4 years). Operat-Ing results led to some minor changes la the detector, which amounts malaly to simplification and replacement of some of the soldered joints by welded ones. R was found that the period of a fault-free operstlos for such a detector working with mir la the central tube of the fuel-pla assembly at about 300T (with the body removed) was much less than that in argon, which is the filling used for the maarlant DMER, since the working life was then only one year.
He seven DMEtt are located in a dry sealed sleeve filled with a mixture of argon and helium. The '
sleeve is set up la a channel analogous to the CPS channels and is cooled with water having an outlet tempera-ture of up to 75T. The sensitive element la a DMEH is the same as in the DMER and is a cylladrical spiral of length 2.6 m. Periodic checks are provided by a tube having sa Internal cavity isolated from the volume of the sleeve placed along the axis. The DMER and DMEN esa be replaced, along with the LAC and LEP chambers, with the reactor working. The maximum currents la the DMER and DMEH at the normal reactor .
power are abod 15 MA.
It is necessary to maintain a reasonably high insulation res!' stance R in la the detectors, since R a h i as a direct effect on the current formattoa la h detector and thus on the accuracy (8]. De lasulation resistance J varies caly slightly durtag the working life sad constitutes 108 -10 e G wth the reactor shd dows for 90-95%
t of b detectors or 10'-10 80 with a reactor power of 25-100% of somlanL If iR a falls below 5'10 8 D, hre is a spontaneous change la the sensitivity of more than 10% that is inrelated to the laput impedance of the f secondary apparatus, which is less than 100 D. De DMER and DMEN are obecked nataly by scanning the l fbel-pin assemblies adjacent to the DMER as wellas the central sleeves of the DMEH with the reactor working by means of small triaxial fission chambers. .
I The secondary electroate equipeneet la the SPMPDR differs from the apparetas la other such systems mately la that it comblaes the functions of maaltoring the power distribdios sad producing signals whea
, permitted levels are exceeded with the fenottom of moeiterlag the relative power estributtaa, which locludes odpotting informattom om deviations from the speelfled distrendloa. The relative power distributton is mon-
,' itored by compartag the reference levels and correspondlag signals for each of the DMER as normalised to W total signal from the DMER. A display la front of k operator presamts signals when the reference levels are exceeded by more than 5 and 10% and when h levels fall by more than 10%. De normalisation reduces the <
errer of the system arising from N lag la the DMER dettag fast abanges in remotor power, while h taforma-
, ties displayed to the operator on the forms of the power distrendios is smaltered as the power changes. De operator oma estimate h deviations from the spectiled relative power distrendios by altertag the reference levels la the relative moattoring ebannel over the range e 195. De total-surrent recorder for the DMER is the mala lastrument for maaltoring the reactor power.
De secondary electronic equipment la the 8PMPDH also combines the fenotions of absolde and relative monitortag of the power distribeloe. He structure of this system differs frees that of b previous one only la that the signal from each DMEH is normalised to the total carrant of the seven DMEH !a one chamael, not to the total current of all detectors.
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o i Th3 SPMPD provides maaltoring of th3 pow:r distributi:a la the range from 10 to 100% cf tb3 sominal l power as w:ll as moaltering cf ths th2rmal pow:r of the reactsr la th3 rangs from 5 to 100%
3 De Skala central monitorlag system [7] is based on a V-3M computer and provides maaltoring, process-lag, display, and recordlag of most of the engiacerlag parameters of the reactor and of the power station as
[s a whole. The signals from the central system are processed by the PRIZMA program, which calculates the l,' power for all the fuel-pla assemblies, the limittag permissible power for each fuel-pla assembly correspond-l
~
lag to a given probability of crists-free operatloa la the assembly, the reserve-power coeffielent Kr relative l to the limiting acceptable power for each fuel-pla assembly and the same for the reactor as a whole, calcula-tion of the steam content la each fuel-pla assembly, the power productica by each assembly and by the reactor
, as a whole, b reactivity margias, the burn-up la the DMER and DMEll, the recommended water flow rates l
through the fool-pla assemblies, the reference and maximal signal levete for the DMER and DMEH, the am-plitudes of the axial harmoales representing height deviations la the energy distributlos at the potatAbearing the DMEli assemblies, overall reactor $arameters (reactor power ladicated by the SPMPD and the best-englaeerlag lastruments, nonuniformity coefficients for b power distributloa, total power and flow rate la ladividual parts of the reactor), the recomumended displacemensa for the control and protectica system rods, etc. PRIZMA also performs the diagnostic processlag for oestala forms of reactor equipment and also ac-cumulates data on the peripherals for subsequent statistical analysis, while providing cycIlc recordlag of data
. for analysis of emergency situations. Any cell la which the calculated or measured parameter (Kr, fuel-pla assembly power, water flow rate, etc.) differs from the specified one is displayed to the operator. The results 9
are printed od as patterns with ladication of the type of each channel (fuel-ple assembly, MC, SAR, AC, DMER,
. etc.) together with the parameters char.nel by chamaels water flow rate, steam content, position of CPS rod.
- The pattern is, accompanied by a brief summary of the general reactor parameters and a list of b 6-10 most j highly stressed fuel-pin assemblies with the maximum power and mialmu
- n Kr. De calculations are per-
- formed la 5-4 min.
8 De software for the operation of the RBMK la deelgaed to overcome the complexity or impossibility of direct moottoring of many parameters, laciudtag ones related to safe operation of b oore. These parameters are maaltored ladirectly by calculations la the Skala system on the basis of results from more complex cal-culations performed by an external Bf3M-6 computer. He data awahangre between the BfSM-4 and the central maaltoring system for the RBMK-1000 at Kursk and Chernobyl suolear power stations is performed adoenatic-ally by means of Aidsord 1200M taterfaces. The software for operstlag the RBMK-1000 includes the following:
( PRIZMA for the la-statton computer, BOKRIB for periodio physical calcalations on the BfSM-6 giving the
(. opimum power distributtaa and the positions of the control rods BOKR, LEN, and KVARTs for BdSM-4 pro-cesslag of the measuressants lavolved la checking the DMER, and ANAf40 for periodio checidag of the .
PRIZMA with b BISM-4.
De profiles fbr the distributlass of parameters such as the fuel-pla power, the channel water Sow rates, and the reference levels la the SPMPD substantially lefluence the safety and economy of the RBMK. A param-eter that la to be used la optimising any of the parameters of the reactor la design and operstlos is obylously the referred cost g per kWh subject to the varteus constralats tamposed primarily by the requirements of power station safety. In ladividas! lastances where most of the parameters have been specified, it is permis-sible to optimise a slagte parameter that lafluences 4. For example, la deGalag the asutual distributions of the power distributtaa and flow rates, one uses the ===d=== probability of crists-free operation la the oore for the RBMK-1000. He basta laput data are here the specined anaerosospic distributlos for the power pro-duction over the radius, which lanuemees the limitleg permiesAsle reactor power, and the specino power pro-duction la the fuel, together with the dyasatto stabilty la the power distribution and the reactivity balance. The specified macroscopio power distribdios is determanad frena optianisation calostations on the external oost-peer for each enlarged state of operettom.
i De sequaisee for controlilag the power distribelos la the RBMK-1000 imelades sheervation on the power distribdios froan the SPMPD signals, the display, and the priated patterms from the special anoeltor, together j with the parameters reisted to b power distributtaa (distributlos of Kr, distributies of the water Sow rates, t i and general loop engtaooring parametere), whtok anar lavolve odydtlag recommendations on changing the water flow rates, the referemos levels la the SPMPD, the positions of the correctors for the CPS abada's, all of which employ recommendations from the oestral anostorlag system. Farther, there may be settons involving direct control of the power distributies by diqplaceaneet of the control rods and by altering the levels of the AC or LAC treasducers, together wth changes la the modes of operation of th's montering and oomtrol systeens ,
(switchlag of the AC and LAC, calls for recordlag SPMPD signals, the calling of oestral montor systema data, i etc.). The number of manual operstless lavolving the CPS rod Is reduced la stattomary state by factors of
, . _ . .. -. - =
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- - , .. . ....umsv wusarve so incas emamat:3 contros.11 powse everload occurs la o fuel-pla casembly, th3 power dirtribution can be regulated with cr w.".hout th31.AC, and th) work of th3 operstar is cimplified is th3 first case. Each retoedlag operation f;r o fuel-pts assembly is p' receded by adjustment of the flow rato la th3 reloading region. Mnual control of the pow r distribution is provided by alt: rants opera-tion of the manual controls and the SAR, which eliminates general reactor or local deviations la radius and s height.
p The moaltoring and control systems thus constitde a hierarchie structure with virtually ladepsaded L base subsystems, which are combined as regards monitoring faaetions by means of the central maaltorlag
\ system, which lies at the top. Such structures provide high reliability and viability la the entire system, but they impose a considerable load on the operator and other staff, who are involved la ensuring ocasistent opera-
~
tion of the individual low-level systems via manual control of the power distribdica and so on.
R has become necessary to improve the control systeams for the power distribelon la b RBMK reactors.
and the following factors are lavolved:
- 1) facreasing the specific thermal loads on the fuel and other parts of the core, with substanilal increase la the number of moaltoring potets and number of control malta for b next generstlos of RBMK (RBMK-1500 and RBMKP-2400):
- 2) the ongolag tightenlag of speelflestions for reactor safety and rollability la nuclear power station .
equipments .
- 3) the need to reduce the load on the operator and to taprove the econospy of the power stations and
- 4) the need for b power statloa to operate la load-tracking modes.
, Experience with the RB'MK-1000 has given rise to practical proposals for improving these reactors: la order to improve the power-distribution control systems, it will be necessary to anske further use of com-paters la the light of the above factors. Extension of the sphere of the comiputere la control lavolves new
, problems, particularly safety aspects. E la necessary to deflee the oorred combination of analog independent systems with systems based on standard computers. One possible approach is a oomablaed saantortug and control system that imelades the CPB tradittomat for the RBMK-1000 that works with the lateral lomisation r' chambers, together with a system for moaRorlag and contretilag the power distribdier. (8MPEN ensploying analog lastruments worklag wth the 252 radial and 80 height internal detectors and providtag local protecties agatast major deviations from the specified margins for avoldtag crists and linear heat loading la the feet-
,_ pin assemblies, together with transmissloa of b sormalised signals front h laternal detectors to the fj analog local adonnatic controls and compdor, and flaally a ocotrol ooanputtag system constattag of several s* sesystems each with its own computer and a higher-level compdor, or else one la which each sesystem eniploys several computers.
Such a system will have a hierarcht'estructure, and the first level aa=e.a== analog systeois (CPS and SMPIM, which normalise and transmit detector signals to the second-levet systaans, which employ compdors and whleh process the data to present leforunation to the operator while providtag automatic management of the energy distethdica (via the cps), as well as diagnoots of equipment states and local emergency protectica
, on the basis of current crisis margtes and heat loeds on k feet-pla assemblies. At the third level there is i
a high-power computer that performs complicated physical and optianlaation omiculations and which provides coepting to the external computer la the power systems.
'Ibe independent digital protection sesystem la the second level calculates the maximen permissible signals from b laternal detectors and oompares these with the current signals, whlek provides a digital protection fumetton, while the CPB and 8MPD provide analog protection. 'I%e control itsettons of the CPS and SMPD back up the analog fumettoes execded by the osotrol computing systeen. The DMER are pawvided by fast seatsetos detectors.of cable type, in whlek the sanitter costalas hafhham, while the DMER are asseunblies of two trianial gaansa chambers. Enok of the to chassels esed in height anestoring eumploys dry sleeves cooled by water la the CP8 loop, and four seek assemblies are set up la each ebammet. A characteristle fen-tare of the system la that it provides local adomatie emnergency protection of the reactor front arroneses removal of any control red. 'Ite systems is designed for completely adematie control of the power distrepe-tica under stattomary and treastemt conditions.
Feare improvement of the automatto emettities and compdor basings for power stations with RBMK should not be accompaaled by an increase la h amoest of laformation odput to the operator, but lastead should involve autoanattag control and odpd'of laformation to the operator only of essential data indicattag f*" . .
, . ee .m eo oh x..
o .~
an'estlous a:aations not envisaged la the moaRoring and control tigerithm3. The operator should be protoded
- from redaedsat rodine tafirmatloa la cad:r to be abla to concentrats attenties on the basic factors that d:',ce-antae the safety and efficiency of the reactor.
LITERATURE CITED i A. P. Aleksandrov and N. A. Dolleabal', At. Energ.,3 No. 8,337 0977).
.g'
- 4. L Ya. Deel'yanov, la: Nuclear Solence and Engineerlag: Reactor Physics and Digineerlag Series, Issue 101) [la Russinal. TsNHatoailaform, Moscow 0979), p. 38.
- 3. I. Ya. Eniel'yanov et lat., At. Energ., g. No. 1, 44 0 977).
- 4. I. Ya. Etnel'yanov et al., la: Nuclear Science and Engineerlag Reactor Physics and hgiacering Series, ~
Issue 1(S) (la Russtaal TsNRatominforan, Moscow 6979), p. 3. '
- 5. L Ya. Enael'yanov et al., At. Energ., & No. 3,303 0973).
- 4. L Ya. Emel'yanov et al., Bild., SJ, No. 1, 73 0 974). ,
- 7. V. L Adas'ho et al., 'Systeams for anoaRorlag and controlllag anglaeortag processes la nuclear power stations by means of control compdore,' hternational Electrotechnical Congress, Moscow, June 1977, Sectica 7 [la Russian).
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x THE LENINGRAD NUCLEAR POWER STATION AND ~
THE OUTLOOK FOR CHANNEL TYPE BWR'8 ,
A . M . Petros 'yants . A . P . Aleksandrov ,
N.A Dollesha t ', 8. M . Feinbe rg ,
- j Yu . M. B,ulkla, I . Ya E mel'yanov ,
A . D. Zhirnov , A . K. Kalogia', -;
l A . Ya. Kramerov. 8. P. Kuanetsov, E . P. Kunegla, K. K. Polushkla, V. 8. Romanenko, A . P. Strotkia.
V M. Fedulenko, V. A. Chebotarev, and O. M. Glaskov High-output uranium-graphite channel type tweetors with thoussads of process channels ("techesin leal chamaels') have been la servios la the USSR for many years. Power reactore of this type gilberian nuclear power station (11) have in en la servios slace 1960 with operstlag temperatures la the neighborW of 200'C and loop pressures up to 80 stan. The remotor of the World's First neelear power station was started up la 1964 (2]. Two nuclear steam superheat reactors have been la aperation at the I. V. Koretet -
nuclear power station at Betyt Yar (one staos 1984, the other staos 1987) at parameters as high as Stet
- j and 90 atm (31. Vast experience has been secumulated to date la the operstloe of those systems.
. The high degree of viability of these reactors, attributable to the possiblittles of effecting monitoris 7 and ooetrol chaamet by chamael, is not a matter of record. These options have made it possible to detect i malisacticalag la tadividual prooses chamaels well la time, se that these channels ena be shut off and re-
~- move:L from servios before malfumetles and damage esa spread on an eatensive and dangerous scalethrvec' out the entire systesa. Methods have been worked out and perfected for shuttlag oE and repairing disesete components and subsystems,lectedtag the graphite staaktag, to the pelat of replachs an of the graphite stacklag la a major overhaut (41. Such a comparatively vulneraMe subsystem as the portlos of the preens channels located within the reactor oore can be soplaced during scheduled preventive malatessace opers-tions, and even with the reactor still on power. Despite possible saata==a'ta== la ladividual channels, thre the reactore have been operated sucesssfuuy,en the whole, for decades of total operstlag thee. -
The development of large-easle high-output moelear power enamot vest solely es esperlesce la der -
alga, but most also be baebed up by a large nuaiber of esporteneatal deelga projoets and related practiest work. Even the performance of ladividual large ecale prototypes enamot aa==*u=4= reliable evidemosef str l Seasibility of dowloplag this type of teactor for large-scale power produetten. Only generaltaation of or years of esperience accumulated by ladustry esa provide the rellahts foundellos useded. Way, the obolos feu on the ornatura -graphite chamael type remoter as. the vehlete for large-eente high output anclear power developaneet, with due attention given met only to the esperlease soeumstated but aise to er j progress : ^ _ c' ^d la nuclear technology. E la of course of pebas acessetty that these be convimetag arguments la support of the view that the tread belag developed will at least met lag heklad or tera out to l be laderlor to other reestor types la terms of soots, rettabilky, preeerehttity of uselaar imot, and se forth
[
We smay now enamorate the adysetages of shammet type remotors: 1) high reliability and viabutty of the enties system thanks to chamael-by-ehmanet mostterlag empebility,and the peestbility of malatenesse and repair c f as ladtvidual process chamael without uneoboduled remotor shutdowns:S the poselbility,la prtaciple, of aehlevlag reliable safety by subdividing the aaa8==* elrestattag leep, with optione of an auto-noemous process chonnel taclodod; 3) virtually unlimited possibilities,la practice, of relatag the power Tol Pt-9Gn4M U
x ___ __ --
3 . .
..W un the basis of modular dealga components; 4) the possibility of buildlag a steam generattag telt -
.aLout recourse to large-size pressure vessels, thereby expanding the paduction espabilities at the same
, . v; 3) available option of organialag refus!!ag operations with the reactor still on power; 4) perspectives ,
O .:suelcar steam suportest; 7) flexibility of the fuel cycle, with the fuel cycle readily adaptable to fluctua-as sa the fuel marketi e.g., the rate of consumptica of natural uranium could be curtailed to a fraction.
4.1 cumple, by utiltalag fuel of higher density or by uslag a saland fuel change (ursalum + thorium), or
- .ny-rator moderator.
The outstanding ~ disadvantage of the channel type reactor is the multiple branching and comparative
..mplexity of the circulation loop. .
Sume design improvements capable of greatly simp!!fylag and contractlag the circulation loop (see wiewl.and contributlag to making the steam generator unit and channel type reactor lato as compact a .
i dage as the steam generator unit plus vessel type reactor, have been forthcomlag. !
The developmentof the traditional type of uranium-graphite' reactors opeas up new perspectives for
- .. dear power development, while the experience accumulated la this area provides a rollable foundatloa.
it.as reactor type may also be used for other purposes, for lastance la the production of energy and desall-
, aiva of sea water (3).
The evolution of high-power utsalusa-graphite reactors is ladissolubly llaked with progress la au-slear engineering and in reactor materials technology. The various pathways of development opea can be xed out agalast the example of the chanaal type ursalum-graplatte reactors, breaking them up lato two groups to facilitat,e the analysis. The first group, centered about the achievement of high thermal efficiency, s y be said to laclude the reactor lastalled la the World's First nuclear power station (1954). the nectors a t1w 1. V. Kurchatov Belyi Yar nuclear power station (1963), the reactor with supercritical coolant param-sicrs now in the design stages. The second group. oestered about improvernents la the fuel cycle, would u.ca leclude the reactors at the Siberian nuclear power statloa (1954) and the RBM-K-1000 type reactors se belag built. la the case of the reactors at the Bely! Yar nuclear power station,it was found possible w proceed to cooling of the tubular fuel eleinents uslag boiling water and superheated steam, eyes though
.: eel-)seketed fuel elements were employed la those applications.
,g Ilelying on the current achievements of nuclear technology la the area of refractory strocalum alloys
[ ,
~ fer pressure tuhlag and Jackets of rod-type fuel elesments with ursalum calde cores la water-cooled y'~ eater-moderated pressure-vessel reactors (4] a decision weg saade to lacurporate such design compo-kats la ursalum-graphite reactors with the object of improadag the fuel cycle over that characterised .
by the use of steel and tubular Asel elements (Boly! Yar power station), and improving the thermal efficiency i
aer that characterised by the use of alumlaum alloys Gilberlaa power station). The proposal to adopt that l i>pe of ooctant was based on the successful operatlag experlease acommutated la the amanagement of bolllag- '
saier teactors with slagne-loop arrangements (Bely! Yar suolear power statica. YK-60 reactor).
It was la this settlag that the RBM-K tioillag-water reactor of high power ratlag), a slagle-loop ~
araalem-graphite reactor, appeared on the scene, uslag stronaluas alloys as the basto structural material J the remotor oore. The designs and materials selected la the ouestuvotles of the f.rst reactor males were sleser to those verifled la earlier practice, even though the possibility of ocasiderable progress la nuclear reactor technology had been apparent fresa the very guiset.
Construetloa of the first power unit of the slagle-loop amolear power statica (LAf8). 70 km west of leslagrad and the largest such unit la the USSR and la Europe altogether,with a rating of 3 GW (el.) sad sue chamael type ursahant-graphits (RBM-K-1000) reactors cooled by bolilag ws:er (Fig.1), is now nearing esopletloa. This power statloa is the pacesetter of a new line of nuclear power stations of its type now unler seastruotloa oomstitutlag the future base for productica of a asajor porties of electrie poser to be i d late the natieast grid la the Europosa sector of the Sevlet Unica.
LAf5 Power Statloa Layout and Basic Parameters
'the ansia hermal of the suelear power station ocasists of two power units rated at 1 GW 4el.). sharing a essames anachlaery roosa and separate resetor bays, systems for ooeveylag Asel, control panels, sad a evenmos room.for gas cleanup and purifloation orthe prisaary-loop water. Each power unit laoorpoistee a BBht-K-1000 reactor with a circulation loop and aualliary systems, steam llaes and condensate-Geodwater hees, and two K-800-48 turbogenerato'rs rated at OJ GW (s!.) each.
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. Fig.1. General view andpanoramt LAf8 acelear power station a egrad.
amar Le le view of the con four y circulation pumps with a set fThe circulation loop ocasis (D = 800,1900), and 22 distrib t o valves and piplag of snediosa diametparalle ng two separator drew
- reactor steam rating,a u or groups common system of headers y (D for = er (D = 300)'and largerest los 300) y exchange sup l .
diameter diameter) to reach the two K-500 45 tSaturate -
s amounting to 45 of the [.
'r pressure rehesters as recycle ssure urblass. to the leaves The d the separators through eight t h fill levet la the separators.
i i
eserstor, and on to the Isodwaterpumps ee b
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,icon v a valves controllingtir kV. The power le provided by switchlag la supplies f for e the local moods of th L IThe turbog 4'{ 4 .
the event of a total power blackA Spower staties comes es rated froan at11e -
the l . ..ge '
power station and from dieset rosagenerat110 and 330 kV power llass rators. through Staedbrpnuet st out power een be obtaland froam aaeyatransformers.
separ t set - -
storage batteriesooseventag ors.whlek valtsswitok whichon emanat asteenstleally toleratelaan a or generatorla athree l
hydroelectri-y aterruption la their power supplies arslautes'thee,' *7powe '
through pressure. Excess steam appearing e seenooted to a bankwhen cf ' ' , ,. th
. r. '
disoberge froan the safety valves ,
valve of soone thenoess or both turidans steam;gis ,,
laclo ro
/h heat for toont spaos at heetlagThe steam is met power vented rattag ser) whlok toalso ofthe a atenceph slagte collects LAIS eI .
feedwater temperature le 148T ower unit is 3.1QW Sk.)and 170Cei!
GW of tie tu tutG*.W ) .l<.,,.
- tith poselble shift to oestrol . The smed saturated steaan pressert . p ea a blood upstressa of c.. . .
saaterlate are: etreetation . Theloop steaun austeattl rate is 5800 tone /h. ne isThe 65 atmoperstla when t'-
steelt osedesser turbing et water MNZh alloy;16bl trestaneet mostral with no correcti g ooeditions are:haar I ** : /*-
eagsteel and stroontenas steam metalileilaos and e of reactor oarbon eteet. ofThe fuel is ursal steelt burnup 18.500 MW-day g / ten. The wei ht f preheaters stataloss satelineseerhos st . ;.
13180 tons uraaluss 1.1% uss dioxide earlehed to 1.8%rostures beatlesary o theeeriched and enric* 9 statloanry feet charge is 180 toes ura looeditie , .-
- or 15 toes ursatum 1.8% eartched.
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e a .
- s Ddfumes welding Electre beam welding
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(voceum contact welding) [
f _ __ _ /
0 09 h . . _. .
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@,m._m4, Fig.4
' Fig. 5 Fig.4. Jotalag of stroontum alloy tube to stabdess steel tube: 1) tube of 010:10N1tr steel; 2) union of bimetal sandwich; 3) alpple adapter. Er + 1.5% Nb alloys 4) tube of Er + 2.5% Nb alloy.
Fig. 5. Placement of proossa chamael la graphite stacklag: Er + 1.5% 14 alloy tube;
' 3,3) outer and laser graphite samull, respectively; 4) graphite stack.
A program of esperimental and lavestigative work and reactor tests. Including heat-transfer sad
' . mice-{lfs tests, were carried out on the feet channels and unodels of fuel assemblies on spee a l l test I aals,and subloop remoter tests weno carried out on a full-elsed fuel assembly,la order to ocefirm the priurmanos quallites of the redesigned v=*= ami subsystems.
Unitorier. Control, and Adjustment of Power Station One of the major problems la the building of the 1AIS power station was how to svold shutdowns of l r ' oower station esospt la extresse ettuations where that recourse is absolutely unavoidable, and, still e to the polat,e!!alaating any chance of remotor shutdown la seaponse to spurious emergoesy signals.
The rebellag system and the systeenbr maalterlag leaks operable with the remotor sa power, are assigned directly or ladiscotty to anellitate that purpose, as is the elimiesties of the brasehod system of
.spelse pressurised water tubes for large-coale chamael by-ehammet moatterlag.minismiantles of shielding i .aihe process equDment where easily triggered pretootles devlees would cause reactor power unit shut-
!.c. as that the protection and contret equipuneet will be activated only when a signal is presset from act
.ms than two (or three) obaamels carrylag measuresseets of tomotor systesa paranneters.
f System scramming wblok would Imsnadiately bring the seacter to suberaticality eyes when as emner-j scy signal is not present le deelgaed for only asse eventualities. Insteed,it was deelded to rely upos .
l a,setalland shieldlag measures espeelatised la terias of speelfle groups of poselble aseidents and malhme-l ;.ast allowlag for a eentrolled drop la power at a sufrieleetly inst rate and to a lovst which weeld guarantee i s#racties of the heat la seeldents and malfumations belonglag to that speelfle greg. If the algaal trigger ng as protective settes disappears, them the power drop to diesentimund and aermal Asestieslag as seousned.
j The radiaties enviromaneet is sensed by the same radiaties seuroes as ase used la psessuse vesamt 88 la the steaan times, yas dad sorrosion prodmote la the F :.ps heillag-water reseters gastruments senslag 0 a--a= ejsetor,etc.). ' Ins activity of vapor
) h8m stream.0 88 and REG st the diseharge sad of the assharges froan the eendemente ejector is empoeted tobe anedorate 63000 Cl/ day) eyes la the event et a 4.sys member of antled fuel elements.thaaks to the system ter presses ammetterlag and senselleg with reaa-W en power.and the systems lasorporattag aa==h aania= et esqdeelve statures and serptive setenties of ,
iisti se setivated sharmaal. f Only these heel asseantdise eestalaing fuel elesments with marked sympleans of leakage wit! he re- l moved and replaced ahead of schedule. Even where a slight leakage le detected these will be as need to t
.hs down the reester, and it will suince stanply to eatenet the fuel assembtles fross the inutty fuel chaamet ' )
.hiuse the refuellag maahlas to set a spoolally designed plug la that shamaet.
D I .- * **
. f l
The fuel channels thout 1700 of them) cre loested
- .eg la tubular passages which are welded to the top and hosta i j '
saetal grids of the reactor (Fig. 3). The top and bottom '
parts of the chamaels are made of statalese steel,while f
1
,, a the esatral tube sized 88 x 4 aus is made of Er + Ife Mb alley exhibillag slette satisfactory mechanical emi car-reeloa-resletast properties. The stroonium part of the chamaet is jolaed to the steel parts by uneans of speelsi !
.e welded steel-stroostum adaptore (Fig. 4) which are suh-jected to tests to deterales their espected length of ser-vlos life. The ohnamot a--ahtaa one feet cluster sie
'*d'" *! i two assemblies. Each bet assembly comprises a, set of 8888m- w*w' 18 fuel elemente, with the feel meat section extending 3.5 mi'" # am la length. The feet element ooselets of a tube 13.5
- # X 0.Samn tasal==atar,anade of siroestem alloy with ermi- .'
dioside pellets. nowater nowrote trough the channels
, / lo adjusted twies dortag the remotor osanpalga to snatch ehanges la the fast shamael power output, by adjeetlas e. -
trol valves lastalled en the proosse piptag. The ervelst i probless is how to estreet host from the graphite stacti r
. ,")'
f i E ,t-8 An arrangessent la whlelt the stasklag la oooled by hest transfer to pressorised tubes (Fig. 5) was deelded are
~
{j with the object of simplifylag the resetor design.
p / De protection and control systeet is deelgaed to j'
d contret someter power dampe at a rate of 4%/see,and sc
- to keep power perforsnames sometaat la the evest of se-e: eldents or usalfumettone set seguirlag shutdows of the re-h actor. When assessary, the rosstor een be shut down completely at a power less rate of 85/sec. The pretee-ties and oomtret systesa snakes use of highly rollable ser -
e ' condeotor and =a=aa=*=a*8=r aa r====*=. Stamitry equir-mest is hetit late the ersteen.
The power solosse mealtortag systesa that moniter' .
the amount of power tituersted wtak sospect to remeter he's v
N and remotor redtes used aestree-seaslag essapemente le-stalled la the parts of the deel ebensels and eksanels ute
- 8f messerlag and semelag oompensata for the preteetles se' Woest la teatret system.
i Fig. 3. Fuel channel: pressurised labe 3) The seendness of the Oset elements is smaaltered.
I shamael passage s 3) bottom ehleidtag plate s and lenke desseted, by messerlag the settvity of the W L 4) support sleeve; 5) adapter (steel-air. -water m'.atuto la the piping at to estramos to the seint-i eenhssa); c) thersaal shield: 1) stacklag
- ters,with the and of palsed a.eans.es== type y-ray pree hlook: 8) fWel assosably: 9) top stileidtag tremetrie sensore seented es unerlag platforsas andi er -
{
} plate 19) feel chamaet head 11) fust es. les!!y sneelterlag the piplag. The water Bowrote throut' sembly seepenelos support; 12) resnovable the shamaels la alas monitored by Asesnotere lastatted i ekleiding plug. -
at the talet to eneh poet shamael and at the talet to the pr teettom and aestret ohnamel. De seendasse of the ekse-nel tubes le anonitored by shooldag the shaages la the property of the gas Bowlag estelde the shno- ,
net. -
I The vapor alstere le elroulated through a elesed leep. The vapor annatuse le purifles! of water tsr
- and produets of graphite omidstlos la the loop, and the prospoolned composities et the alme6:e le elee s
- tered and analataleed at its properlevels.
Seane of the resetor systesa esoponents were devolepod. la the course,ef deelgalag the reeeter.In '
approsehos similar to those used la the design of ea=ya===*= which have made a good name for themsels
- l over an extended period of operattag history with remotore of this type. [
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[- f amasser asis b .- Fig. 2. 8ectica through reactor and multiple otroulation loop: 1) oore; 2) water supply ,
llass; 3) steam-water mixture bleed llass; 4) steam separator; 5) pump; 6) rebellag -
machlae. I
! He characteristles of the basto prooses equipeneet Sa the power unit) are: separation gravitational
.a horisontal stataloss steel clad separator drumaidrumdiameter 2.3 m. dran length ~30 sa drum weight M tons, four drum separators la all; alght punaps oestelbgal electrically powered pumps with sealed .
,.mp shst outlet and Sywheel, throughout 7000 mm8 /h at head of 200 m HgO and 1000 rpaa. weight !aeluding ,
4340 kW electric motor ~100 tons; two saturated stesan turbines type K-000-45, slagle-shan, double-Sow see high pressure oyote and four low-pressure oyotes), turbise length 20 an. shat speed 2000 rpm weight
! 1310 tons; stesas separator and steam reheater both located between high-pressure oyotes and low-pressure l 4,cle; two 800 MW 4el.) generators three-phase. Se oyotes/see with hydrogen coollag and water ooollag.
~
I Foer ohnaast systemas are used la the RBM-K system,with the poselbility of settlag up a refueltag e:eseen operable with the reactor on power. This makes it possible to ratas the land factor of the emolear emer staties and lower emproductivity losses la the aboostere of the protection sad control tred) systema.
.nlaise to maalmine vapor discharges through the poselbility of detoottag severs antleres or leaks la het '
.eesablies and replaolag these faulty assenbiles proanptly. 'Ibe weight of the rebellag anschloe, sbloidtag Ateded. le ~408 tons.
assetor Deelta .
The resoter le loested la a comorete pit 21.s x 214 x 25.5 m. De weight of the reactor is transmitted aihe esecrete via wolded unetallic structures wblok almultaneously perform the bootles of shieldlag and
- de. together with the emelosure envelope, a cavity filled with a helium-altrogen misture constituttag the ,
7.-* 'er space withis wblok the graphite stacklag is secommodated (Fig.2). The graphite stacidag ooselets
. phite blocks with cylledrical holes aspembled la columes. The columnas are jolaed by cooled beams .
! elating outward la holes ta the peripheral columas. .
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Fig. S. Variants la arrangoment of cemonende Scrge pumpe sad headore elimiested): '
s a) astural-flow separation; b) forca*.' flow separation (fAf8 power p'.ant variant in- '
c 7
dicated by dot-dsch 11 ass); 1) corvi 2) water surfy liase: 3) steama-anut malatere ex- '
tractica lines; 4) steem separator; 5) pamp.
Fig. 't. Section of modular varlet of RBM-K type reactor. . '
i
( .c. y Control of power station performance le deelsmd for base lonh sad a followup made by so csle8-c 'N the pressure upstream of the turbbt!ata setpotatthrough aedom of the controller on a throthe vobe lie operation at base lond) or on the reactor power controller 01:he followg anode). Operstlose.1 up-to-t' minute maaltoring and control of the power hellities le her.aN try cmputer and data-precose 95 sasrM*- -
Muelear Safety .;
Some features guaranteelag r ndlettom safety are built lato the someter systeen kaus .
- 1) high-reliability protection at ocedrol system factedlag sent 144 8% tty acting abt+t- '
combined with groups with autonomeous e moore, cables, comparisen ogntysment,equipenes.' for es@t r '
elssale, and power supplies;
- 3) eqelpanent for emergency heat removal flywheele es do pwho*palhop puunpe, stead;n purt sources for local asede, routlag et f wdwaterto a discharge header etc.), ellolanting any large-se di- <
y i i '
to the cladding of the foot elesmente due to any er all of the l#sted eso,e o! neokinete er malfmster* 'i A lootedlag total power blackout, outage of two turblaas etaultuoust,leanu la piplag c f M (M we d+ -
eter,etc. Even complete rupture of piptag of that rue outsW fic 4;rouade J Ik 7AN Hwi'Mallee M
- i, saa be handled safely through these mermraat , v .
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~ :l) equipment f r maklag periodic checks on the state and functioning of all the subsystems and sys-ams responsible for maintaining radiattoa safety, including periodic checkouts of the state of large vessels
.: ibeaders, thereby practically eliminatlag any lastantaneous total rupture of the equipment or total break-4a; e plenum chambers and surge tanks for steam, to eliminate large-scale veaung of steam to the
.masphere la emergencies.
k la also 15sportant to note that there will be no dangerous positive reactivity surge la response to 3+ a. klad of damage, accident, or failure affecting the circulation loop. .
C.
Generalization of the operstlag experience acquired with conventional pressure-vessel machinery
,1 aJ uraatum-graphite channel type reactors already la operation la the USSIt shows that a suddea lastaa-( pi nacous faibre or burst of large-diameter piping and of drums designed to specifications and fabricated in
.w.formity with accepted technology of high-pressure unfired vessels is extremely unlikely at the moderate
,,wasures and temperatures f avolved, and given the latensity and quality of the inspection and monitorlag gocesses.
Leaks la theprimary loop have been observed. But these leaks developed at a comparatively slow use and la no icatance IM to an lastantaneous rupture of large-diameter piping, even though breaks la smaller piping 1-2 cm la diamatar often result from corrosion and vibration effects. To cope with this.
i cuures were taken to laatitute emergency coollag of the core and to eliminate any damage to fuel ele-
. a. cats or release of flastos products lato the power statlas rooms or late the surroundlags. With the present l
. uing of nuclear reactor power generating stations near large cities and the corresponding public-health aluo zone assund the plaats, the reactors are for practical purposes completely sale with regard to the
.quistions of the nearby localities, as is clearly evident when examtalag the case of the Belyi Yar nuclear 3 r aer station which has been la operstlos and generstlag power slace 1984 {7].
Im2rovements la Circulation Loop and Enhanced gudca r' Ja f e ty Future plans for building a large number of reactors that necessarily have to be situated closer to c' ' p fe.ge populattom osaters, and where the public-bealth isolaties soas around the nuclear plaat will have
)q u ts cuatracted, the problem of further improvements la the level of nuclear safety typifying nuclear power (eurattag stations oomes up on the ageada.
\ '
Analysis of the oossequences of failures of 300 sam diameter pipe has demonstrated that a large vol-j of water and stears is discharged when the water volumne of the loop is combleed, and that it is difficult i ulucallte this dis:harge without severe addluomal losses. But it is precisely the chamael reactor deelga
'g .hich opens up the possibility. la principle,of flading a successful solutten to this saasty problem. Here (i .Lsre is ao need to comblas the water volume of the entire reactor as is the osse la pressure-vessel type reactors. Ou the contrary, the analysis shows that the small mamahar of high-power pumps can be reduced l % a large atmher of low-rattag pumpe, that large headore and branches la the loop ran be allminated by nt iing lastead on a large number of separate sootlooswklek are sufflaiently sa-- la their operstloa.
it< avsettlag ooanpilastlos of the control system is not that great, but a la!!urs la the loop is la any case
~
L.calued within the ocafines of one seottom of the loop. The existence of communioations between different
( auctLac of the loop la patre does not blader such localisattaa of damage and failure, so that these stessa l -[ '
.- ImLa la it:a loop osa be retalmed without worry. -
l 1x.al-Sow turboseparators with a high steaan load per salt volusse, and jet pumps with a comparatively I.w abroughput. are widely used la1the pressure-vessel type bot!!ag-water reactore.
, Fragnatatattua of the circulattom loop brings up the possibility of complete malasaotionlag of the val-h ses. headers, ans large-diameter pipes,while the use of turbooeparators also anabes it poselble to situate p aN la ter la vessets of modereas diasseter. 'Ite seamparatively small amenet of water presset la esak b-i utlet of the loop. poselbly oes-teeth or even one-hundredth the annoust present la convestlosal loops, or kas,faellitates accomunodalloa and localisatlos of eteaan and water la the event of any disruption of the
\ % ,
in eddities to the potats made above, the fragmentation of the loop and the use of small-elas separa-y, x
) ws aise rukes it possible to locate these machlass closer to the reactor, thereby reduelag the length of ,
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1 -
TABLE 1. Basic Characteristics of RBM-K Type Reactors -
C' ,,,,,,,,,,,,,
Parametess BSM-K-1900 RBM-K-3000 ROM T P-2000 esitteel para-enesses tr}
si!' " Power susput.WW:
e le ctrica L . . . . . . . . . . . . . . . . . . . . . . . . lokt 20fD -2000
- r 81M
' eno rma l . . . . . . . . . . . . . . . . . . . . . . . . . . 3339 S alta 3 020 2 350 Sesam paramesses upstream of terWees -
peessure. ata. . . . . . . . . . . . . . . . . . . . . . . m 85 06 340 d',r,'MEterna:::::::::::.:::: a a & & '
i' ,5/3.WAs","Ww.viu:::::::::
Feel.............................
it*in L4mide a
Dioalde A
Dionida
.J.
CarWee-Peak chaemet output.kW . . . . . . . . . . . . . . . 3coe 8Is0 gag 4360 Stgaasupesh 4400 ii reak heat nom 10' heal /m'.h. . . . . . . . . . . . e.7 e,s o.s 2.5 Feel treadistsee lawt. w.f/ sos. . . . . . . . . . . . 11,8 19.s 19,2 44 Feel-element cladding material . . . . . . . . . . . Zisessies : :Ziecesissa Eleosalem seest i -seest b,
the outgoing steam piping runs by a factor of three or four. This also results la improved laterchannel stability in circulattoa, slace stability varies in inverse proportion to the steam volume, and sinos Jt is IV vapor tension of the steam vold that is responsible for the development of pulsetions in Rowrote. This deelga solution based on fragr.vantation of the loop witit the use of turbooeparators and closer siting dthr.
turboseparators to the reactor is a way of contractics the volumns of the loop.contractlag the water volan of the loop, and cuttlag down on the amount of metal regelred la that part of the plant by a factor of two at three. .
Of course the large puraps have to be replaced by a large muunber of smaatler punnps of suitable fig-Teodwn'er pumps la such varlaats as steam-Jet heat psamps and hydraulically driven pumps are comvnic+
only when the multiplicity of recirculatloa la small, and electrically drivea pumaps with coastaat sh!3 rpm Q 1ead to annoylagly rapid drops la steam contest when the power faus off, se that a largs reserve supple of water is required under the separator level,dich as tuta sneens that there would be no father sale la owitching to small-sise high-latensity separators such as turbo-steam separators. The use of steam-driven turbopumps tacorporated lato the loop fr ths ferie of a vertical slagle-shaft unit,with the pump im-peller located below floor level and the turbios drive located above door level, favors snore conipactnes*
and improved safety la the operation of the circulation loop. Those paaps have no shaft outlet, are awk more compact sad mud lighter thea electrically driven pumps. samt esklidt the importsat properties d 5 proportionality of rpm and pump throughput to the Soweste of steaan frosa the resotor. That is what all==
us to get my without posittoalag the pump la a very deep obaft, wtslie curtaillag the water reeerre is the separator several tinies, and also alLTss as to resort to osnergemey cooldows setoonstloa!!y. through the agear p of ponderous Bywheel saasses (Fig. 6). .
) A tesleally new system for estreettag itent frera the feet chamaels has been worked out more recev+
y one whM opeas up the possibility of Isrtherradientadaptiftonttrashthseireulatlau loop. As ther weight Sowrate of the two-phase coolant doorena.r. the orttleet assan= eastent and the critical burnout 1eede is-eresse. A "multitlered" arrangement of organisation of host'rrsanovalis fuel chamaels,with thyInst ebn-L an!.s diennenbered along their height into sevetst " tiers' communicating with es water feed limes and re" entraetloa lines located withis the pressurised tubes la a parstlet arssagement. Les been proposed. The weight Soweste of coolmat la each seek " tier" would be reaktood by as sesmy times as the number of " tiers
- the fuel chamaet is broken up lato, provided thare la uc change la the tots', Sow area g rM by the ert a
~
. section of the assenably of fuel elements.
l 4
! The rise la steam ooetent tat the operattag potat) to 385, and eves to s05, outs dows ene member d I eyoles of otroulation through the loop that is required by a inotor of two to three, and the hydroelle reste-
! tamoe pressated by the fuel chamaels doeresses to roughly 5-6 atm. Staos the power esad up la oirevistl t l the oootaat is proportional to the pebduct of the otroalation smeldpilofty factor by the bj. draatte reelstaner.
! the power drops so low that the use of jet peeps with hos4 copplied by the feedwater peeps beoosses se e effective procedure. The principal radioactive e1rometan leap of the remotor is thereby freed frem ant l ased of mechaalcal pmaps, which samman simpler oportalom atd cheaper operating oosts.
' ~
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- Moreover, the amount of water la the remotor oore is also out back onesiderably, sad is largely re-Jaced by steam. 'Ibe depth of Asel buraup laoreases and the physion1 stability of the plant le lamproved. -
- f. . since the operating polat beooanes displaced toward the region of higher steam vold content. The amount V
J aetal used la the destga of the oire=I=*aan loop, and the volusse of room space takes g by the otrouta-as loop, are both out book oonsiderably.
- ranium -G raphite Reactors belag Developed The usatoriallastles of some comoopts on improvements laRBN-K-1000 type reactors found renootton a the designs of the RBM-K-2000 reactors and the RBM-KP-2000 steam superheat reactors rated at 2 GW d.). h contrast to the RBM-K-1000 type, these remotor types were designed with sosted-up channels.
she evaporstloa channels la these resotor types are deelgaed almost identloally, while the Aset elements
- - se identical with those la the RBM-K-1000. The design of the reactor oores differs for the most part only athe presenos of the steam superheat chamaets la the RBM-KP-3000 reactor design. That also accounts l Jr the difference la the process Rowsheets. The prinolpal charseteristles of the RBM-K-2000 reactor ;
se are listed here la Table 1. 'the auelear power plant Bowoheet is bestos!!y similar to the Sowsheet
.erked out for the RBM-K-1000 remator power plaat.
Withis the conflaes of the reactor oore, the evaporation chamast is a stepped a5 air, made of strooalum has,with the large-diameter tube loosted above the oester of the oore. The expansion of the diameter Jthe stroontum tube la the some of latease s' team generstles allows for placemoet of lateasifiers, improve-anats ia the conditus governing oootlag of the top of the fust asarsabiles. laoroaslag reserve marglas up J eritical burnout levels, and also g estly reduolag the hydraulle resistamos presented by the chamael as a dele.
The suolear steam superheat shamael features two-way Sow of coolaat. The saturated steam Dowing beaward through the outer annular elearamos cools the chsanet tube.so that it saa he anbricated of air-mium a!!oy. Steam superheat is aehleved la the laser telescoplag portlos of the chamael, where the feel !
Jeemblies are positidned. The Asel assesably consprises a tube of =8.salaan steel sised 10.x OJ mm. Glied
- f. ., sah uranium diealde pellets.
'the chaamalsarea-=a ame elaa aqsare grid with a pitek of 320 anan. The total number of shnamels
[% J1404. of which 1060 are evaporstles shamaets Svap Ch la '1%ble 1) and 254 are steam superheat channels ilsam Superk la Table 1). Forced-Gow soollag of the stacklag by otroulatlag altregen is plaaned with la- ;
Jensed pitch between the chamaels uad laoreased spectSo power output la the RBM-MP-3000 generstlos Jreactors. The blowers and heat eschangers of the gas coollag streaan are built directly lato the reactor
,, asiosure. ,
V Cootaat airculattom through the evaporation chamael and steam superheat shamaels is headled by the ,
, 1 shopumpe lastalled la the druan-esparators. The protection and control systeam of the RBM-KP-3000 motor la contrast to that of the RBM-K-1000, uses contret rods situated outside the grid of feet .a-tm , '
. 3s absortdag part of the rod is usado la the forma of slags of boren earbido la a graphite unstria.
( ,
{ The rode unovo on special paths under the setlos of push rods laserted below tan reactor. Coollag
, aby gas otroulatlag through the osollag systeamit the resetor staaklag.
t
< i
- n. l E5 orts to mamma =mina the etReleasy of the amolear power station led to the completed design of a re-Jeor adapted to supererittoat coolmat paranneters. Some of the design characteristles of the 1000 MW ist.)
maluma-graphite reactor produolag steaan of agerorittent parameters are laeluded la Table 1. ,
8 l l ha evaluattag the oost ladines'of the amolear power stations based on shaanet type remeters,we saa i de clearly that these power ma naama are not laderlor la soot performanos to suelear power stations based l
a renators of other types, suok as gas oooled grapMte-anoderated remotors, or water-cooled water-moder-ad remotore.
(
1.rge-.oai. ausi.ar ,ower de,si.,m.at brings to me fore me probi.m of oriaMang ind trat men-A et anbricateca sad assembly of the remotore Efforts to imorease remeter unit power output pose the prob-Ja of worttias out a resotor deelga such that remotors of laoreastagly higher output retlage oma be bout l et alaimuna chaages and without radical restructurlag of the produellom foollities and plant. Ia.. em the i 7; asis of untttsed and sitandardised anodules and structural deelgas. The possibt!!tles laborest la eksamet ,
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r f type ursalum-graphite reactors make it possible to find solutions to this problem. The first step taken is that direction is the design plan for a sectionalised modular eranium-graphite chsenet type reactor.
The reactor is assembled from standard sections: central sad edge sections jotaed according to a prospeelfled plan at the rigging and erection site. The core forms a rectangle la plan view. The length of the rectangle is determiend by the number of central reactor sections (Fig. 7). A reactor of practicatir !
any power rating can be built from those sections simply by lacreasing the number of contral'oecticas. Tir sections functica as separate component units of the reactor system. and tacorporate the necessary eqelp-meat plus control and monitorlag hardware, and consist of ladividual transportable modules. The width of the section is determlaed by the diameter of the separator.
Some Possibilities laherent to the Fuist Cvele One of the principal features and advantages of channel type reactors is the broad range of applicatie-of the different fuel cycles. The possibility of refuellag with the reactor on power, channal-by-chmanel process monitoring. and the comparatively low multiplication factor, combias to open up new pathways for flealble control of the fuel cycle.
Depending on the future conjuncture regardlag procurement and ralalag of natural ursalum, e.g.. la ;
case the price of natural uranium rises, conversica to utilisattom of fuel elements with desser (la urasismi meat cores combloed with comparatively low burnup is an option st!!! opea. This makes it possible to lose needs for procuring natural ursalum by lacrosslag the U" buraup ratio, and also by uslag ursalem of sht- l 1% enrichment, which may be economically feasible. Plutantosa breeding is another possiblitty, and mat gala la importance as the power output of fast reactors leeresser. Without moosesitettag a chsage in de- '
sign. It would also be possitde to effect a treasillom to thortuna composities with U" or UM. The fueleyr6 l osa be improved by lowering the operstlag pressure (which would maka it possible to this out the walls of the channel tubes and the oladdlag of the fuel elements) and by outtlag down en the amount of water pen-eat la the process chmanets by increastag the steam volane.
[ Finally, !! even greater savlags la astural ersaiwa resources are noosemary, it would be possible to
,v replace all or much of the graphite anoderator by heavy-water moderstor.while retalalag the haste de-sign and process Sowsheet features of the reactor.
I i Curtallment of the volume of water sad structural materials la the core by lowering the pressure and by improving the technology of refractory aircoalum a!!oys wn! eentribute to building g reserves.ese?
' a long period for gradus! taprovements la the fuel cycle and oo.._ , _ _
outbook of the fuel componrat la electrio power generstlos costs, it should also be potated out.'
The chamaal type reactors now belag developed are thus seem to be n thia and adaptable to possilk changes, even difficult-to-predict changes, la the outlook for natural erantes procuremsat, and platenlea -
breedlag demands. This means that we esa ocasider the presset developmental outlook of chamael type reactors to hold good for a protracted period of thee ahead.
The data cited above. and the possiblittles of haprowlag the remotor design and foot cycle.altoe as
(
to espress ocafidence that muelear power generstlag statione of the Imatagrad type now belag butt will be.
l to begin with.cocoomically competitive with power stations burning foss5 emets anywhere on the terrim of the Europosa part of the USSR bot to speak of the appreciable by-prodest of adrastages to the sottomt economy la keeplag the atmosphere free froma pollution by aa-t==*los prodents, and the ocasiderehle sav-lage, la cost and la available raesIns of treasportation, la =t=f=ining leag-heat ablpments of helb and secondly these reactors are at the very least not !aferior to other hesis types of power remotors bad sure thmes eyes surpass the latter la perforsnaaee).
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P. A. Lavdansky C,(
F. S. Neshumov Yu. V. Ponomarev A. P. Kirillov V. S. Konviz .
tonstruction ofifuelear Power Plants / -
Edited by I Professor V. Dubrovsky, D.Sc. (Eng.)
Translated from the Russian by A. Kuznetsov .
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j 16 cnAPrER oNE lb Table 1-2 within a BTVR vessel is chosen according located a cc j$ 14ading Particulars of Soviet. Built PWRs to the conditions of internal steam sepa- necting coolt
- d ration and the neutron flux stability the fuel chani y . ,, . := and is usually about 7.0 MPa. through the r 9 5 7 9 F'TrrapMte-moderated reactors. These haves ne supply g;p p"
E E
g 5
g found wide application in nuclear poweF plants because they can be fueled with'
.cinel heads. '
..r, appropria he ri,of of th natural slightly enriched metallic uras!
N Capacity, htW: nium or uranium dioxide, show a highej .ncath the el.<trical 210 365 440 1000 conversion coefficient than LWRs, cart . rive mechan I::t thermal 760 1320 1375 2MO use high-temperature gas coolants togeth- Tho weight 34 er with graphite, and also can be refuele6 ' e'. the coner en 27.6 27.6 32 L~ Turbine inlet without shutting down the reactor. structures wh in biological; d saturated ste-am pressm, Graphite-moderated reactors may be of pressure-vessel and pressure-tube type. the enclosure 4' '
graphite-moderated space filled '
Pr a ure within In Pressure-vessel reactor ves- reactors, the coolant is carbon dioxide, and nitrogen a% sel,3!Pa 10.0 10.5 12.5 17.0 helium or, though seldom, other gases :;raphite bric Number of cir- (these may be called gas-graphite reac- In the wate
% ed reactors .
F H
$'t stain #circula.
6 8 6 4 tors), whereas in pressure-tube reactors, the coolant is light water (these are known NPP (see T.
h ting pump d*lgery, as water-graphite reactors).
A major drawback of graphite-moderat- rau 1-3 5 000 5 600 6 500 17 000 ed reactors is that graphite is exposed 9 Power per tur- I,ading Partic to high temperatures and considerable 1 bine, atW 70 73 220 500 neutron fluxes, so it must be very pure, e;rapi,ite. Mode at siclayarsk .5 uniform in structure, and stable against 4 radiation. Also, the pressure tubes must g the reactor vessel. On top of the core is be properly proportioned, aligned and , , , ,"
b.t installed a steam separator assembly held in a strictly vertical position, and
., .y A
forming a cylindrical cavity between the vast number of independent coolant the core and separators, known as the circuits must be highly reliable.
A water-cooled, graphite-moderated w
upper chamber or plenum. From the upper plenum, a mixture of steam and reactor comprises a set of fuel channels capacity, 3 w thermal In liquid water passes through the steam inserted into holes in a stack of inter- 'I'ctrical M separators where most of the water is connected graphite bricks serving as the MI '/j',3j ,
g removed (the humidity of the steam moderator and the reflector. The graphite does not exceed 10%). The steam then stack is contained within an air tight on loop ,
Power per t 13
', p goes to a dryer assembly located at the vessel filled with an inert gas at a pres "
top of the reactor vessel, which removes sure close to atmospheric. The load ;
51W E,,'l haht,:
o p,E d the remaining water. . Imposed by the dead-weight of the core 4 ruel Both PWRs and BWRs are refueled is taken up by a bottom support slab. Weight of belek stock,a f;*8 after the reactor has been shut down and A top slab similar to the bottom support 3bjget jn,9t nt f; its pressure reduced. For this purpose, slab rests on a water-filled tank which
. w. the cover is removed and the steam provides a thermal shield for the concret* temperatu separator assembly is extracted together biologleal shielding. Between the roof of pressure, j with the upper plenum lid. The pressure the reactor section and the top sleb is
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' 17 NUCLEAR POWER PLANT aT5TEMs AND COMPONENTS toented a coolant supply system con- steam is produced directly in the fuel
.nl ng necting coolant headers (manifolds) to channels. For this purpose, the core hu l
,4cpa- l the fuel channels. The fuel channels pass channels of two types, namely evaporst-
.i.;tity through the space occupied by the cool- ing channels and superheating channels. ,
mt supply system and terminate in ina the former, mixture waterand of steam is converted to liquid water,
..have.
.mver' efuel heads. The channels are refueled by which is passed to a separator where the n appropriate mechanism installed on J with- he roof of the reactor section. The space water is removed. The steam then goes .
uras' .' aneath the reactor contains control rod to the superheating channels and exits t
.,;.. hey: from the reactor at a temperature of
. rive mechanisms.
n geth.
cne ! ~"The weight of the reactor is transferred 480*C and a pressure of 9 IVIPs (this is
'o 'the concrete through welded metal known as nuclear steam superheat). As it -
..tueled i .
structures which are simultaneously used passes through the core, the steam 1,ecom-in biological shielding and, together with es radioactive, so the turbine condensers,
. It be the enclosure, form an air-tight reactor live steam pipelines, and other auxiliary
.. type, 8 Pace filled with a mixture of helium equipment of such nuclear power plants
.. rated and ultrogen and containing the stack of should be enclosed within biological
.i., side, .
shielding.
.- gases graphite bricks. Advanced reactors of the above type In the water-cooled, graphite-moderat-
... rene. ed reactors installed at the Beloyarsk have simplified pressure-tube circuits (a
..,,c tors, NPP (see Table 12), the superheated once through coolant system), show an 1:nown improved neutron balance owing to the use of zirconium instead of stainlesssteel
. lerat- Te We 1-2 a ng a cons rab neubnopture
.' /
Leading Particulars of Water-Cooled cross section, use the more conventional
~il Graphite Moderated Reactors Instally uranium dioxide fuel clad in sitconium,
% pue, at Heloyersk NPP have an increased unit capacity, and l '
! ...vinst can be refueled almost continuously. In
,4 must
= *r ;d the USSR, such reactors designated ,
....I and ^'"*d*" 9 {g RBh!K (for "high-power pressure tube l ...n. and gg reactor") (Fig.1-4) are in operation at l .noinnt 3 3 many nuclear power plants (for example.
i '
Leningrad, Kursk, Smolensk, and Cherno-l ..i..ra t ed capaetty, MW: bylsk).
thermal 286 530 2 220 I t..mnels 100 200 t oo0 Soviet-built high power pressure-tube electrical
.I inter. Overalt e!!!ciency. % 36.3 37.8 45 reactors exist in several modifications a the
- differing in capacities as listed in Tab-
)r.iphite oNps
- 2 t i le 13. In the last two modifications, iir-tight Power per turbine, provision is made for steam superheat.
' MW $00 t00 500 a pres. core dismeter, m 7.2 10.2 The RBMKP-2400 (Fig.1-5) is an
.c load *8 ** outcome of an effort to develop a reactor the core $1 Weight of ho' hc design that can readily be adapted to in-
.rt stab. brick stack,tgraphite 810 1200 dustrinlized fabrication and assembly
, support Turbine inlet steam methods and whose unit capacity can be
. k which e
- " varied to meet specific power require-
.nnerste te "Iuro.
ra *C 500 540 ments. The reactor is assembled from roof of pressure, MPa 9.0 24.0 type-design central and end sections.
.. slab is 3-41101
,_ ____ i_
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98 CHAPTER THREE .
g,d 3 (see Fig. 3-14). The reactor blocks (A folds or 50-mm and B) face each other with their trans- supplying water
- port entrances. The space between the tubes. Under g
mzu g reactor blocks is occupied by auxi- pressure tubes a liary systems and repair services. In ad- flow water fron Det t n dition, the reactor section includes the When any oth pump station and the evaporation plant forced circulatic
- y @ of a liquid-waste storage facility, and a tor core is coole
- gas-activity suppression plant which is reactor cooldow
. qI j located directly under the central span -a group of pn 4
/ roof. Owing to auch an arrangement, ex- to each group i
- M neting valves; i
Mq dg ternal ventilation services are no longer
-a feedwater a t
needed and the stack can be located on b # E the roof of the reactor section directly of feedwater at lP f above the general ventilation systems pumps; l
and air purification plants. -a system for f Outside the main building are located supply from a
[yb N'dh (b)
- d. " " clean" and " foul" condensate tanks, storage tanks for liquid wastes to be soll-dified, and solid-waste repositories.
pond.
Free steam di break is ensure The layout of transport facilities signi- densing unit. 4 ficantly differs from that used at Kursk. bubbler pond 1
/ n 3-15. La[en"skt of the first stages at (a) Kursk an$. 9) At 12.0-m elevation, the reactor section the reactor sha
' smo multiple forced has through horizontal transport and process communications to which are water intended the blocks making up the main building connected the locations lying above and released from t' differ from one another in design and below, the central repair ahop, external as the suction arrangement. The transport and process transport communications, and the cen- the main circul.
communications, especially between the tral entrance into the machine room. two levels. In a reactor and the liquid-waste treatment The reactor section is connected to the system of heat system, and between the gas-activity liquid- and solid-waste storage facili- cool this water, suppression system and the atack, are ties via a covered elevated passageway heat can be extremely complex. Solid wastes may accommodating pipelines and storage- bubbler pond u be moved to the storage facilities only ry car aisles. down complete, .
by motor vehicles, so there must be a Present-day safety regulations for nu- The bubbler special garage and a washer. All auxi- clear power plants require that the core ns an independ liary structures of the reactor section are should reliably be cooled down in the the emergency 2 regarded es " hot"-sone locations. case of a break in any, even the largest, As an alterna At the first stage of the Smolensk nu- pipeline ~ In the coolant circulation cir. handling the at clear power plant, the types of the main cult, and that such accidents should be dent.may be le process equipment and the arrangement ' confined within a given circuit. block. In this e of the reactor sections proper are the In contrast to pressure-vessel stations should be muel
! same, but the layout of the main building where the severest, accident is a break in dition to the at
. has undergono a significant change. Four a major pipeline in the multiple forced air expelled fro section of the e blocks (A, B, C, and F) differing in ar- circulation circuit, the most serious ra.
rangement have been replaced by a single diation hazard at RBMK-1000 reactor tions and tunn block measuring 72 x 102 m in plan plants is a break in 300-mm group mani- .
to the condens 3
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..r blocks (A folds or 50-mm . bottom water pipelines A further step in the field of high- @j C u eupplying water directly to the pressure power pressure-tube reactor stations is d
.. their trans- !-
!,etween the
.. ! by auxi-t u bes. Under the circumstances, . the the development of a power-generatine pressure tubes are cooled down by back- unit with a capacity of 2 000 to 2 400MV
[.h g j ',
. ieco. In ad- w water from drum separators. ,
where the increased unit capacity will ,
j .
includes the When any other section of the multiple be supplemented by a nuclear superheat S l
. ration plant forced circulation circuit fails, the reac- system capable of raising the steam to ';
ility, and a tor core is cooled down by nu emergency 450'C. This will considerably raise the
..mt which is reactor cooldown system comprising efficiency of the plant and make it poe- Q.. I-central span -a group of pressurized tanks connected sible to use high power turbines as instal- :
.nwment, ex- to each group manifold through quick- led at fossil-fueled thermal power sta- i d .
- ine no longer acting valves; tions. 3
- .e located on -a feedwater supply system consisting A problem that again arises in connec- .
u
. iion directly of feedwater and emergency feedwater tion with 2 000 to 2 400-MWe 'RBMKP j !j tion systems pumps; reactor plants is the reasonable limit, j 2
-a system for emergency cooling water for the size of the blocks into which va- b Q
- are located supply from a large-capacity bubbler l rious sections of an NPP can be combined. l h
nute tanks, ",nd. As experience shows, already at RBMK- i j b
is ree steam discharge during a pipeline 1000 reactor plants some areas lie outside
'es to bo soll- '
.4itorieg. break is ensured by an appropriate con- the reach of the cranes installed around d:
densing unit. At Smolensk, this is a cilities signi- the perimeter of the main building. ! i' hubbler pond located directly beneath
" ursk. Figure 3-16 shows two alternative ar- '
2
.c .I(r : tion the reactor shaft and the cells of the rangements for the main buildings of a [l r o.., . and multiplo forced circulation circuit. The nuclear power plant using RBMKP-2400 i g ..
which are water intended to condense the steam reactors and K-1200-65/3000 turbines. :
pl, k s above and released from the largest pipeline (such Referring to the figure, in the first ,
n
- p. external as the suction or pressure manifolds of alternative, the turbines are positioned Wlj ,'
, ..d the cen- the main circulating pumps) is stored at along the building, and the machine room l
,ine room. two levels. In addition, the plant has a of one power-generating unit is the con-l l . ted to the system of heat exchangers intended to tinuation of that of the other unit.
g
[M j,
i y .
l ..-ige facili- tool this water, so that all of the residual IIere, the total length of the main bull. E.'
! ;iassagoway heat can be withdrawn through the ding in each stage of the plant exceeds [ i }-
hubbler pond imtil the reactor is cooled 300 m.
I ...I storage. .
jg i-*-
1 I An completely. In the second alternative, the turbines ..
4 9 i .as for nu- The bubbler pond may also be are positioned across the machine room j[ p.
..t the core I ' a$ an independent source of water for which is a three-bay building. The outer . ; g
- .n in the i;.elargest, the emergency reactor cooldown system. bays of the machine room accommodate As an alternative, the condensing unit the turbines, and the central bay, auxi-
% u
!.ition cir- handling the steam released in an acci- liary systems (such as the deserator moun- %'ilL hU .
.hould be ilent may be located outside the reactor ting frame and the like). The machine -
i j ' .U-air, block. In this case, however, its volume room in this case is less than 150 m
-,I stations should be much greater because, in ad- long, and is only slightly wider than i
- i break in dition to the steam, it has to treat the the reactor section. Such an arrangement gi,.
l@ forced t air expelled from the cells in the failing cuts down the length of pipes and cables, f, wrious rn- wtion of the circuit and from all loca- and simplifies the layout of the site and iJ ,
lions and tunnels connecting these cells i erection c.onditions for the main bull- l m reactor ,
- ..up mant- to the condensing unit. s ding. ; o t
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di 2;# Fig.14. Crose-sectionalview of an RBMM.iOOO reactor station building (reactor shaft) 3-steel block.s; t-ordinary concrete; J-tron-bartum-serpentiniteternent block; d=eerpentfalta; d--easd; #== ,
, water g ;
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% central sections used. The reactor sections crete vessel is shown in Fig.1-6.
- are readily transportable and self-con- Special promise for nuclear power ap-6}' tained as they come complete with all pears to be held out by fast breeder Fig.1-5. Bu!!dle l the controls, monitors, and other accee- reactort, or simply, fast reactors. As al-soe==-= uones ,
ready mentioned, they both generate
> series.
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- refort. As al- Fig.1-5. Building of an RBbf KP-2400 reactor station tal crose-sectional view; el) plan * -ettom separator; t-group headers; -typer watet pipeltnes' d -stesm s-suction header; s-apper block; F-delivery benders; s-main cIrtslattns t flgeld*
e sl}t gener3(3 *
' , 8 ), (0 !)ftPal, water misture s-l ressure header;pipcitnes;feedwater as- header; ss-reactor core ss-bottom repair mechantsm; ss-tower
.is..stee block;; se- atas-b.ubble.r pond; so-saturated steam header; st-sug.=ebented steam header; ss
..i.,unble mate. pipeiine bestms t
secuen; ss-o.ur ted steam pipeiines; se-refueiins mechenporsuon , I geh s i.g.- o o. ine ceu; as .apetwaun t he coolant in - - .
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nation, are confined in ' hot"-sone loca- nuclear power plant of this type is prac-y tions. For better connection between these tically always ready to operate and la j systems and the systems located inside very safe. The use of slightly enriched -
j$
?
the containment under seismic condi. uranium cuts down the share of the fuel tions, the containment and the shield in the cost of generated energy.
mgl --
f building are supported by the same base- Among the major drawbacks of pree.
W plate. The arrangement of the packaged sure-tube reactors are the complex and -
t systems within the reactor section shield bulky coolant circulation circuit and a ,_
i building also helps to cut down the length large number of auxiliary systems. This
- 4 of services and piping to a minimum, complicates servicing, calls for excessive j Loads are moved into the containment scarce materials for pipelines and other
- and the shield building by a rail track, and equipment and for larger volumes of
- g handled by appropriate cranes. structural materials per installed kilo- '
y The machino room houses one t-MW watt, and increases the overhead item t' o turbogenerator. The transverse span of in the prime cost of electric energy.
6 the machine room is 51 m. The mainte- Because of this, nuclear power plants $ .-
? nance floor of the turbine is at +15.0-m based on pressure-tube reactors are more i elevation. The turbine compartment is advantageous than nuclear power planta M.c,,,de -
t 108 m long. Along row A, the machine of other types only when the unit capacity -
M
.?
7 room has an aisle for vehicles.
A through rail track runs within 18 m of the reactors used is high.
The main equipment of such nuclear
. #~
p g of axis 1 to provide enough space for the power plants (Figs. 313 and 3-14 inclu- p
,4 assembly of the generator stator. des a high power pressure-tube ) reactor
~
The total length of the machine room, and a multiple forced circulation circuit including space for dismantling the equip. made up of two loops each comprising i
ment during repair, is 156 m. two drum separators and four main circe-The deaerator frame having a span of lating pumps with pipelines and group ng. 3-12. Gei 11 12.0 m adjoins the machine room on the headers from which the water is sup- ,--mm imum 3 reactor side. The deaerator is installed plied to the pressure tubes. Each reactor ';"#,yl,',$$
3 at 34.2-m eleyation. is ganged up with two type K-500-65/3000 J turbines.
Each turbine has a system for with-tes four tur?
A,$ 3 3. Pressure Tube Reactor Plants densate pur 4 y drawal of up to 75 Gkal h-8 of heat to dium pressu
$m RBMK 1000 (1000-MWe pressure-tube) supply the plant itself, the near by real- emergency i reactor power-generating units are rather dential areas and other local consumers . The spac d popular in the USSR. Such units are 175). '
machine roc d used at Kursk, Chernobylsk and Smo
- The reactors together with their mul- i frame whosi i
lensk (Fig. 3-12). At present, the Igna- tiple forced circulation circuits are each -
deacrators
%* lina RBMK-1500 reactor plant is being located in separate blocks between which t,,wer floort 5 built and a power-generating unit based are installed auxiliary systems inclu- . unit contro l ',-
on type RBMKP reactors with a unit ding a " foul" water purification system ring board:
l capacity of 2 000 to 2 400 MW is being with a water supply control board, an I,atteries, c
.J developed. air purification unit, a radioactive gas trie equipt S Because the core consists of a large and aerosol treatment unit, various work- . The mot g number of continuously monitored small- shops, and the like.
- accommodo e section fuel channels, and the reactor can The machine room is common to two peopic and 1 be refueled without shutting down, a power-generating units. It accommode- ) urs which 1
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7,ggger:'Ei itaENs "Na'nTer'IoilE'e%EUeI'Ee'rIeYilIf it e 05/3000
- hot
- and " cool" locations of the reactor k [E1 tes four turbogenerators, and also a con- and machine rooms with the office bull- N
'"r whh- densate purification unit, low- and me- ding. !
C dium pressure heaters, feed water pumps, C
- iliestto rest- emergency feedwater electric pumps, etc.
Because RDMK-1000 reactor stations have a single-circuit steam supply system, b U
'."'y""'" The space between the reactor and 0 .c
. most of their process systems are located :-
's i
- machine rooms is occupied by a mounting in the " hot
- sone. The " cool" sones of P j.
, l'g' ""g{ frame whose upper floors are taken up by such stations mainly contain electric 1
.ei [, $ h decerators and a pipe aisle, and the equipment, plenum ventilation systems. 1 lower flo rs by a central control board, and other auxiliary units which do not '
. " inct"" unit control boards, dosimetry monito- come in direct contact with radioactive L
' .i ring boards, house switchgear, storage {T T" *systern -
batteries, cable shelves, and other elec- media.
- d. en Most systems located in the unattended j
~'
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" a. work- rooms of the " hot" sone are contained inj !
The mounting frame also serves to isolated cells, so they may be inspected '
- accommodate the main passageways for and repaired without shutting down the *
,, to tw"
- people and vehicles, stairs, and eleva- ! f.
..mmodo- ors which independently connect the power-generating unit. The processs equip-I i P
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r maximum safe levels specified for such room is taken as 51 m to give enough 7 3 ,!i.*assembled locations. space to the turbine, its auxiliary sys-
.!cring repair.
[
6 Accoriling to the category of attended tems (such as steam separators and si premi.e s. the respective exhaust venti- reheaters, regenerative heaters, etc.), ma. atm external :
1 9 lation systems are equipped with spe- intenance aisles, and vehicle passages. munications.
! d cial nerosol filters or with aerosol and The height of the machine room depends At the Smc iodine filters. Af ter it has been purIIIed on the total height of the turbine. Also, using four turl
{i ,!j ..f one turbog l j; in the filters, the air is discharged via it should provide enough headroom to carry the bulkiest and heaviest parts of d.c generator L the stack to the atmosphere.
The machine room and the reactor . equipment over the turbine during as. . Jensate-purifi
( ..t Fmnd and tb section have each a ventilation system of sembly and repair, i f ':'
J its own. The intake air enters the machi- As a rule, the heaviest part of a tur.
- ne room through ventilation chambers bogenerator is the generator rotor whose ,,
an internal ra r, actor sectio located along the exterior wall of row A. weight may be as high as 200 t. The , equipment rej 1
4 machine roon
- c't In winter, the intake air is warmed up by t air heaters. From the machine room, the but turbine rotor in it is larger is size.
not so heavy (160 t), {platforms whi rail and mot
( ]4 i .t air goes via excessive-pressure valves to The machine room has two standard s the turbino, condensate-purification, and overhead travelling cranes with a 11! ', in the cou t bubbler cells, and then is discharged ting capacity of 125/20 t each. The rotors . nance on one without special purification through the of the generators and turbines are lifted i unil8 It ms3 f- $ stack to the atmosphere. by the two cranes working together, 5 simultam 1 4 in the reactor section, each group of with the help of a spreader bar. For this .".nf onei turbin i d nance of the locations has an individual plenum ven- purpose, the height of the machine room 44Mc 2- tilation system. Here, the intake air is somewhat increased. If use is made of - case. the are i- is first purified in filters (in winter, it one overhead travelling crane with a components o
- .!* might be as 1 is warmed up in air heaters), passed via greater lif ting capacity, the height of 3 air ducts in the maintenance aisles, and the machine room may be reduced by which signifi admitted to the locations to be ventilated 4 m, but the skeleton of the building area of the as i rpace on the 4 'q through excessive-pressure valves. All should be strengthened appropriately.
% the plenum ventilation systems in the In each particular case, the type and the turbines.
- rive spread c P q reactor section are equipped with ap- number of cranes should be determined propriate filters. by a technical and economic analysis.
- is usual to p
! O. forms betwu:
! c All semi. attended locations which may Long machine rooms may use gantry
- be visited for a short time by operating cranes in which one track is installed on . porary or per l4 t y)i and maintenance personnel wearing frog the columns of the deserator mounting ; carry a press
+ suits are ventilated with pure air sup- frame, and the other on the turbine ser . In view of J
'nivisable to i
+- % plied by appropriate ventilation systems. vicing floor, in which case the load '
When designing nuclear power plants, bearing structures are the walls of the .- rem for a la rating units,
'. special attention should be given to the turbine cells and low trestles between g recond stages I arrangement of the process equipment them. In this case, the skeleton of the ; I'hl8 8pproac t-
~v and location of transport misles, so that machine room is much lighter, but the ' I"asible beca
': 'I they would facilitate assembly and re. crane has to be custom made. P"wer plant I; d '
pair operations. Thelength of the machine room depends 3 This is quite easily coped with in the on the length of the turbogenerators and . f"ugr a from changeun y 3 machine room. At RBMK 1000 reactor the minimum distances that must be 3 '
'"achine roor
-1 stations, the turbines are positioned along lef t betwun the adjacent units to accom-the building. The span of the machine modate auxillary systems, platforms for ,f,jh*3gfher
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Fig. 3-14. Plan of the malo buildlog at Smolensk . G radioactivity of the steam condensate W 6
]'
ment and controls of such systems are af ter it has been treated in the conden- fej
\ actuated remotely from maintenance als- sale purification system is low, and the i[
i les, or have a built in electric drive. level of radiation in such locations is jd,h g
The systems are controlled automatically much below that in the cells of the tur- 15 i ,
73 J as f ar as possible.
The radioactivity in the machine room bine auxiliary systems.
The ventilation system in the main V l 'e i
j and the mounting frame depends on the building Is designed according to the f.y F ,..
"- p f activity of the steam, which rapidly falls division of the main building locations li ;;*.
i off as the steam passes from the reactor Into " hot" and " cool" ones.
l d;
.i ,.
to the primary stage of the turbine. in the " cool" sone, as in any other in-i .
1
.l
't
' t:
In the immediate vicinity of the turbine dustrial premises, the function of the h l ',,.
l i
' enclosure the level of radintion is insigni- ventilation system is to maintain a spe- ph d d g' ficant and no biological shield is required. clIIed temperature, humidity, and dust Il J 3f f,
' The level of radiation is relatively cc stent of the air,The rooms in the mid-d{i, - high in the intermediate steam super- die e ction of the mounting frame (such where atten-f I
heating and separation equipment and as th- control board rooms)f thektime are
.g 9 in the regenerative system of the tur- ding personnel stays most o y 1 :,. .
,i l bine, especially where the steam is con- equipped with an air conditioning system : ! .
- I densed. Because of this, these systems are including a cooling chamber. 3 located in cells surrounded by a biolo- In " hot" sono locations, the ventila- l I
~] : and the cells are regarded as tion system is additionally required to - - :d j
(* . gical shield, locations. prevent any rise in the concentration of unattended !b Deserstors, bubblers and pipeline als- any radioactive substances above the' d l
.l les are likewise isoleted, although the I
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. suu.ntxos tor NUCLEAR PoM*ER PLANTS 97 j disassembled parts of the equipment designed to accommodate two power- p
]g,[s$8s. during repair, assembly platforms, and generating units. g, ,
- r. tors and The arrangement of the process equip- : :-; i
..ic.), ma. also external and internal transport com. ment and layout of transport aisles in ; j munications.
~
,,g At the Smolensk nuclear power plant the reactor section and associated aystems
, , . . ,,3;nds
,p j7 using four turbines (Fig. 3-14), the length present a more difficult problem.
se. Also' of one turbogenerator cell is 96 m. On At early RBMK reactor stations two !
- I '
o ;
..itoom t the generator side, the cell adjoins con- types were predominant in the arrange- .J:
., parts of densate-purification cells. Between the ment of the main and auxiliary systems.
. airing cs. second and third turbogenerators is laid They were either located in separate bull- l an internal rail track which connects the dings (such as reactor blocks, radwaste- i t of a tur, .
reactor section with the central " foul". water purification units, air purification tor whose equipment repair shop. The ends of the units, uncondensed-gas activity suppres- L. .,,
- ,,o t. The machine room accommodate assembly sion systems, liquid- and solid waste ;c e4 j t t (160 t)* platforms which are served by external storage facilities, and so'on) or combined in a single structure. g .
rail and motor roads, '
s
. siendard In the course of preventive mainte. The former design alternative facili.
,gegi a tit. nance on one of the power generating tates the division of a nuclear. power II - 0
,7[,sr:t:rs ', r
, ,,re lifted units, it may prove necessary to carry plant into " hot" and " cool". sones,' acci. :W out simultaneously a general overhaul dent containment, and erection and as- y 1,'
. u,gether, of one turbino and laspection or mainte- sembly operations. In this case, however, '
- i. For this nance of the other turbine. In auch a the plant site has a large number of 9
. ! in,. r: m case, the area required to lay out the separate buildings and structures, which I,/ f.
i- , og 8 components of the disassembled turbines increases the length of various servicas y .1 might be as large as 4 000 to 4 500 m* between them, complicates the commu-t a d
b, .. of which significantly exceeds the total nication acheme of the. plant, and, final- !t
. loc'ed by ;-
l . . building area of the assembly platforms and free ly, calls for larger quantitles of construe.
space on the maintenance platform of tion materials and a larger area for the '
f.
(;,
l .mpriately. the turbines. In order to avoid exces- nuclear power plant.
. typa and
.!,termined sin spread of assembly platforms, it With time and experience, the latter F s is usual to provide reserve repair plat- alternative has proved to be preferable. 9 e an: lysis.
t forms between the turbine cells on tem. This may be illustrated by a comparison ,
L k
,m. gantry porary or permanent floors designed to of the main buildings in the first stages f p , f.
atall:d on carry a pressure of 40 kN m-8 at Kursk and Smolensk (15] (Fig. 315). Jr .
- m:unting In view of the foregoing, it appears The main building of the first stago p p ,,
turbt:ater. advisable to build a common machine 'at Kurak consists of six blocks, namely y 6;'
the I:ad. room for a large number of power-gene- a machine room (block D) with a desera. .
r
-. ills cf the rating units, as is done at the first and tor mounting frame (block E), two reac- j
,,+ between I second stages at Kursk and Chernobylsk. tor sections (blocks A and B), an auxi-i.. ton cf the i t ',
This approach, however, is not always liary system compartment -(block . ,
er. but the feasible because an expanding nuclear and repair service compartment (block . ny power plant may use equipment diffe- Outside the main building are locate ,..
.. .m depends ring from unit to unit, which may call some of the liquid waste treatment equip- @ r
.ratsrs and for a change in the arrangement of the ment with a pump station and an evapo- i
. aust be machine room as regards its span and
- ration unit, an uncondensed gas activity to accom. height. Therefore, the main , buildings suppression unit,*a ' stack, and liquid-telforms for of IIBMK reactor plants are typically and solid wute storage facilities. All 4 ,,
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radiation-stable pj such plants regt, Fig. 316. Design alternatives for the plan of an RB.\f KP.2400 reactor building steel then prcas (e) turbogenerators actme the tullding: lH turbogenerators along the buildipt; l-R ENK P *40e reactor- Lions.
etteviatina pumpi J-k*l!00 4F3000 turbine; d generator; 4-deserstor; s-trenatorvoer, F=ttrculation#-mals water d ucts t
- T 3
5 266 APPENDICES 3
_y A ppuadaz 6-2
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B Temporary Buildings and Structures FII- chemical tnsulation area FIII- gas supply facilities I- t10/6-kV substation IX - garages II - stone storage facility X - washery
'111-chief power engineer's offlee -
XI - reenagerial offices I
IV - structural element assembly area XII-locomotive depot F- managerial office storage facilities Xllt - electric equipment assembly and wit.
FI - heat-generating equipment assembly tag area area X/ F - espbelt-concrete' plant
- 4 '
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APPENDICES 267 i
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is XXIV - ninforcement plant t XY - fuel and lubricant storage facilities XX Y - demountable boute building plant XVI- construction machine depot P' X Vil - canteen XXYi- portable boiler [i l
X V//l - beat insulation assembly area 0 XIX - construction storage facilities Leg,od *4 XX - wood working plant 1 - buildings and structune: 2 - sheds; J - A X XI - canteen temporary rail roads; d - crane tracks; J - 4 s,.I m ir. XXII - concrete plant motor roads; 8 - fence $
XXIll - pref ab<oncrete yard m
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.cseg Appendis64
[
- CP31 Diagram for Construction of an W P.,
RB31K.1000 Reactor Plant i Jr1f pur 4th gwr 1 Jih watr ist svar EM par 1 i 2 E' E E 1 E' E 1*' E' E E M$*N# ! 1 l X'E I\ E E 1
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ment 8743 Closure of access openings
[ ., 0J Preparation of slu l 4 0-2 Construction of motor and rail I S I6S roads Bleek D .
J e4-4 Construction of water cupply 89-71 Noving work 0-7 C[ns ruYtfon of te my TFTd Constmcun of cuente r, aft and horizontal water. proofing gy,yg buildings and structures Erection of foundauons along 75-77 yggg axes A, D, C and B IE#
Bleen A TJ40 Eration of machine room and Q deserstor mouaung frame ygg7
'*E 34 Earth-moving work Erection of interior structures 3 p.n Construction of foundation 3G47 jjg,yyg k # "
np o e!Yva'u'on 31,3d Erwuo of on on and cella gy,yg 7
- l 14 13 Auembly of metal structural elementa in reactor wetion dof turbogenerator No'Ent 14
$"'*g',' I33'NI ygyy up to 56.2-m elevation
.f g 17 3 Installation of auxillary equip- fsj $$at on tur generator JWdo 88 Pr a $ly f set S 90-#2 don of ' crane No i la 31 n 2 23 3 Construction of enclosure for nad Erwuo .'o e No. 2 in machtne room Jd2.Jd3 y ructor pussembly s&sp.de aNbly of set OP 8#48 I",,II8g tion of Process equ!p-J
- 443 I tlon of turbogenerator 3 2 Pr ab y of set C ,
i 32-34 Ad ustment of at C 3343 Erecbon el celllags la calls
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[I d J p Pa mb y of IOK J S J01 d "
es A and M ASdf Delivery of ut E 101 10s Erection of structural elements j ds.dd Preassembly of set E of machine room and desera.
d4 43 Welding of channels tor mounting frame 4 dd.d8.J33, Installation of unit No.1 in 10310d Erection of laterior structures
]4 49 block shaft Delivery of set r 105 106 in deserator mounting frame Erecuan of foundation and cells sosJ Preassembly of set r of tarbogenerator No. 3 i #142 Installation of at r N # #
Block C 107 103 Earth-moving work
-u #34d Earth-moving work Laying of foundation Laying of foundation 1084 n jl ,
sdas 37 40 Erection of structural elements nJ41d Erection of structural elements i.p to 15.0 m elevation
. up to 8.2-m elevation JJg.JJs Erection of structural elementa k #641 Erection of structural elements gp w 38.2-m elevation 3 up to 17.2-m elevadon 118 4 17 Delivery of unit No. 2 .
,h gl.n Erection of structural elements JJg41# Preessembly of unit No. 2
.a . up to 32.0-m elevation s .
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n APPINDICES 273
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Continsed y I
7tet. No. Operettons ,
~
Ret. No. Operettons F
. i. sip- ~
Y.I NfH3-Nd Construction of shipping canal
..- Block F 147 # 8 Construction of feedwater sta-no.#J Construction and erection ope, tion and other structures a*
rations H9-151 #8 Strengthening of inlet and out.
let of water canal banks (R
- 2-I33 Construction of pump stations i ,.i
- f *- raft On-IAe-3ff e le6s No.1 and No. 2. and instel- ,,
- * *U"E J21 n2 Construction of stand-by boller ladon of equipment at station -;
l' along n3-nd Construction of stack Construction of so d d liquid JJd-N3 Co etion of water-supply o and 125-n9 i structures. pressure other projects; instagod tionand of t[!
I-
- 8-117 Installation o $ pmentand t!O kV I""# I""' no nd Installation of ulpment at station No, t outdoor switchgear 156 n7 Fil$ng of pond Y,,.,
.J lastallation operations
.. . cells JJf-DJ Construction of combined aux!.
e,"g e,gt, J33-137 Prestartfag Precedsres liary building '
g
- d 133 Installation of equi ment 138 M9 Hydrostatic tests. flushing 5
- HO Construction of autilary struc. 160 183 Startmp of reactor and power- r-l."
-[ tures generating equiprnent -!,
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- l gr Nf HJ Construction et dam. Installa, tion of drainage system Jf' equip-
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f.
. , I El.ECTMIC FOWER .
FIME PREVENTION SHORTCOMINGS AT ELECTRIC F0WsR STATIONS Alma-Ata KAZAKHSTANSKAYA FRAVDA in Russian I Apr 82 p 4
/ Article by R. Nursettov, chief of the department of the State Fire Inspection Administration of the Kasakh SSR Ministry of Internal Atfairs: " Order - a Barrier to Fires Frettans of Fire Frevention 'at Power Industry Facilities"[
/Irxr7 At electric power stations, which are the heart of industry's Topply of electricity, the development of power units that are safe trom a fire point of view sad protective means and measures, In which commection prevent fires from happening, are of utmost importance.
with this,new standards have been created and the esisting standards are being reezamined. A great deal of attention is being given to the problem of safety equipment for fighting fires at these key faci-lities.
There are several ways to reduce the threat of fire. This includge I
the selection and rating of electrical shielding, the appropriate execution and placement of the power units themselves, the use of fireproof coverings, and the adoption of effective alara systems and ,
firefighting methods.
It is necessa'rypto discuss this because fire prevention requirements are still beidg violated during the designing, installation and op, era-tion of power units. For example, a great deal of the designing.p/tk in the Kazakh SSR for the construction of new and the modermination and espansion of existing electric power stations. is done by the Cea-11-Union tral Asian Department of the TNIFIeaergoprom Institute estry7,. la Scientific-Research and Design lastitute of the Power I the designs that they do there are frequent digressions from the
- caist ing fire prevention requirements.
There are serious violations of norms in the designs for the construc-tion of the skibastumskaya GRES, which we,re done by the Novosibirsk branch of the Teploelektro'proyekt YCPI thermal electric power sta-Design lastitute73 there tion designing branch of the All-Union tate are also serious. problems in the design for the construction of the Southern Kazgkhstanskays CRES, which was done by the samegorganisation. :
/ '
g Fo I A-%-3M GM _
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L s
tu several cases the designers stipulate the use of constructies ma-terials that are inexpensive, but which from a fire point of view are more dangerous. Errors are committed in the estimates for the distance ui evacuation routes and in determining the amount of water required for extinguishing a fire. Provision is not always made for the in-ytsilation of automatic units for detecting and ext'lageishing fires.
This is essentially the consequence of the poor organisation ef tech-nical training of specialists and delays in informing them of changes a n .! additions to the existing norms. Of course, there are also in-stances of an irreponsible attitude of the specialists toward the work that they are doing and of poor management over the quality of desigas.
Of considerable importance is how the fire prevention regime is ob-served at the facilities. In this regard the Dahambulskaya CRES can serve as an example. But sometimes one can see facilities where the surrounding territory and facilities are cluttered with trash, where the equipment has malfunctioned, and where labor discipline is poor.
It is easy to understand that it is at such facilities where most often fires occur.
There have been quite a few violations of fire prevention practices at the construction site of the skibastusskaya CRES (the general com-tractor is the Ekibastuzenergostroy .
Trust gkibastus electric power station construction trust /). It is no acci[ dentthat in 1981 alone
' there were several fires at these power stations; one of the fires b
cost the state 60,000 rubles. All the same the needed regime is be-s a t, maintained at a low level.
Frequently there are a large number of omissions and unfinished work on fire pne y.mtia2 features at power facilities that have been sub-mitted for handover to the customer. Often this can be explaimed by the fact thatj the builders, in beginning to erect a facility accord-ing to an idcomplete design, do not have an opportunity to order:4he needed asterials and equipment on a timely basis. Thus even aWft'he moment of construction a significant flaw is built into the facility, which forces them at a later time to take additional measures on the tire prevention aspects.
It is these kinds of shortcomings that are evident in the Teatekskays j
T &.T s in Karagandinskaya Oblast, where several facilities and the fuel I :il storage site were not equipped with automatic fire extinguishing l sysicas.
et course, the problem here was not just in the omissions of the de-signers and builders, but in the fact that the TETs administration was not duly concerned about fire prevention and accepted serious shortcomingp.e ,
V For A-sc o -33s-
_ Ge q 19
. 7.M i.e.'
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- 2.) ~
.J
'f j NUCLEAR POWER l:'pj
,, g.
, ;* - *'(.
- 4?
, :,,y l BOOK: EXAMINATION OF AES SAFETY REGULATIONS d, Moscow SOMRANITE POSTANOVLENIT PRAVITEL'STVA SSst in Ruesiaa No 20, 1964 f-pp 355-364 ,y
[ Authorization of de.ree and Article 107 from booklet: " Collection of Deerees 3.r.
of the USSR Covernment", ' Examination of Safety Regulations in Bealear Power 7 Planta",Indstel'atvo"Yuridicheskayaliteratura", Moscow,24pp.J . ._ g *
(Text] ARTIC1.E 107-Authorisation of a Decree of the ~. L, .,
USSR State Committee for Safety in the Atomic Power Indee- .,
's try '
{ .'.
The USSR Council of Ministers resolves ~
i^
To approve the accompanying Resolution of ./. ,,
the State Committee for Safety in the . , g
' .g Atomic Power Industry. , (.
Chairman. - y. 5 USSR Council of Ministers 4'
P t Nikolay Aleksandrovich Tikhonov Suoerintendent of Affairs l
l
,
- USKE Council of Ministers '
[-)lI}'
' Mikhail Sergeyevich Smirtyubov [s ;. j
.Y l Moscow, the Kremlin, 4 May 1984 No 409 .:
w..
Authorised by decree of the ,-
l USAR Council of Ministers l ,
as of 4 May 1984, No 409 I
RESOLUTION ),) "
OF THE USSR STATE COMMITTEE FOR SAFETT IN THE ATOMIC POWER IMlUSTRY ,
.]."
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- 1. Cosatomenergonadsor (State Committee for Safety in the Atomic Fount ledse-try] is an all-union agency of governsontal administration. _ '. ; '.
Cosatomenernonadsor carries out its work in the national econciey is esporvisi safety practices in nucicar power production facilities, febh* =mahme i power plants of any designation (nuclear power plante, nuclear central hostin5 ".1 h;-
and power plante, nuclest heat supply stations etc.), experimental and research T5 and davelopment nuclear reactors, and in the area of nuclear safety, sad also of . ...aar power plants on ships and other floating equipment.
'Ihe entirety of Cosatomenergonadsor's work regarding problems withis.its competence must he directed toward safeguarding the intereste of tbs state, ky; preventing accidents at nucicar power f acilities, which accidents estall the ;4 escape of radioactive products or ionizing radiation above the standards set se for normal operation. It also sees tt, the detection and analvais of the causes of thene accidents and takes the cecessary preventive acasures. Finally, it sees to the improvement of the operational reliability and safety of all the nucJete power production facility equipment under its contr 1.,
Coestonenergonadsor bears the responsibility for organizing and carrying out systematic and effective of ficial supervision of safe working practicas in the nuclear power industry.
p 2. Cosatneenermonadzor's main tasks are:
of ficial supervision of the observance by all ministries, departaeats, enterprimes, organizations, institutions and officials of established rules, standards and instructions for nuclear and technical safety in the plamains, erection and operation of nuclear power facilities, in the designing and name-facture of equipment for these facilities, and in the storage and transport l
of nuclear fuel and radioactive wastes at the indicated facilitiest ,
monitoring the development by ministries and departments, based on the .;4 recuiremants oT scientific and technical progress, of standsrdising technical, ..
specifications to insure the safe operation of nuclear power facilities; 4 ;
to monitor the quality of equipment manufacture for all nuclear power facilities, and the garrying out, in the established sequence, of special '
technical receipt of basic nuclear power station equipment, including equiposet .
l annufactured cooperatively at the enterprises of member-countries of SET l
l Council for Mutual Econcele Aid) and the Socialist Federated gepublic of ,k Tuaoslavia, for nuclear power stations erected in the USSR and abroad with the technical assistance of the Soviet Union; @
the monitoring, according to an established sequence, of the quality of the construction of nuclear power f acilities, and of the installation of equip- j) meat at these facilities; 6 9
monitoring.the carryina out of measures for accident prevention at seclear power facilities, and preparing enterprises for the elimination of these actid ,
, dents;
/
I 66
. LE r '. -d
=
1 l
l monitoring the accounting of nuclear fissionable materials at auclear power production facilities.
- 3. Cosatosenergonadsor carries out its of ficial supervisory duties directly, and throuah regional agencies formed by it in an established order (edsimistre-tions of districts and inspectorates), and carries out acceptance of equipment for nuclear power stations in SEV member-nations and in the socialist Feder-ated Republic of Yugoslavia, through specialists which it has sent abroad.
Cosatomenernonadsor is comprised of Cosatomenergonadsor and its regional agen-cies.
- 4 Cosatomenergonadzor is guided in its endeavors by the laws of the USSR, by the other resolutions of the USSR Suprese Soviet and its Presidium, by the decrees and regulations of the USSR Council of Ministers, by this decree j_ and other formal standardizing documents relating to its scope, and by the recommendations of interdepartmental technical councils, and it insures correct apolication of the operative legislation in subdepartmental organisatissa.
7 Cosatomenereonadzor disseminates the practice of applying the legislation 2 of safety in the nuclear power industry and develops proposals for its i_,;ese ment, and submits them in an established sequence for the examination of the l USSR Council of Hinisters.
- 5. In accordance with the taske entrusted to it Cosatomenergonadzor:
a) in interaction with the USSR State Committee for Science and Tech-nology and the USSR State Committee for Atomic Energy Use, coordinates the
- scientific research conducted by the ministries and departments which is directed at validating the requirements for safety at nuclear power productico i facilities, and validating the ef fectiveness of designs used to insure the f
m safety of these facilities. Here, the scientific guidance for the research
- into the safety of ncelear power production facilities is provided by the l .
Institute for Nuclear Power iment I. V. Kurchatov; exas('nes and approves the list of rules and standards for safety and ,
b) the plans for their development with the appropriate ministries and depart-J l I
ments; c) with the appropriate ministries and departments, it supervises the deve lo pment of safety rules and standards which are applicable during the
- planning, erection and operation of nuclear power production f acilities, and durina the design, manuf acture, installation and repair of equipment under e the control of these f acilities, and approves them in an established order; d) supervisen the development of sectoral standardizing and technical documents on nuclear power industry safety, including operating instructions for nuclear power producing facilities;
.) 67 E I u 1
wl r
e) makes dectsions on plans for state and sectoral standards beving to do with problems of safety in nuclear power; f) checks on the observation and analyses the effectiveness of resplations and norms for nuclear power safetyr durina the planning, erection, operation and taking onclear power facilities out of operation; durina the designina, manufacture, installation and repair of agsipment, instruments and products which are under Committee control; durina the transportation and storage of nuclear fuel and radioactive westes at facilities under Committee control; i g) sonttors the cheervance of plannina, design specification and tech-nological documentation requirements, and of regulations, norms and instructione durina construction of nuclear power facilities, and during the nomsfecture, storaae, installation, testing, operation and repair of equipment, instrussets and products for these facilities; h) monitors the carryina cut of measures to eliminate design and opera-J tional flaws and to improve the safety of nuclear power planta and impeoes
} the quality of the manufacture, installation and repair of equipment, lastre-
> ments and products for these units; i) examinas proposals of ministries and departments on the submissias of rules for plannina nuclear power facilities and designing their equipment to enterprises and organisations within their jurisdiction, adopts the appr#
rate resolutions and also grants the enterprises and organisations the right to manufacture, install and repair equipment for nuclear power facilities, when the necessary conditions for completing the indicated work exists j) regtstars nuclear power facilities and grants permission to operate '
them when positige decisions are forthcoming from other official supervisory ,
agenetes durf n's the month following presentation of the required satarials #
's l (permission is subject to reapproval after five years and following every case of accident);
k) registers nuclear power facilities' pressurized equipment sad piptag, and gives permission for their operation and checks to see that they are cer-rectly and promptly given their technical inspections by enterprises and orgam-trations;
- 1) examines the following, which have been submitted by the sialstries
, and departments for approval:
detail designs for reactor plants for nuclear power stations, shape and other floating equipment and experimental and research nuclear reactors; 68 1.) E
{
data which substantiate the selection of: construction sites for ==ela=r
- power planls, experimental, and research and development neelmar reesters, also plans for the erection of nuclear power facilities, in the sphere of coordinatica thea with safety rules and standards: g-r m) examines and approves the following lists, sutuaitted by ministries I and departments: tL lists of enterprises and organizations under the Committee's controls )
lists of equipment, instruments and products which are esb. ject to a:.g special technical acceptance; ,
.g; n) establishes t5e sequence and volume of operations for cwa = ognipment A and systees for nuclear power facilities and for the special technical accer tance operations carried out by the Committee. 94 h
e:K
- 6. In order to accomplish the tasks set before it, and to fulfill the A=*taa h' entrusted to it, Cosatomenergonadsor has been granted the right toi a) to conduct, at any time, checks of all facilities is its jurisdictica concerning problems included in the Committee's sphere of competences b) to bring in, in coordination with the corresponding alaistries med departments, their enterprises, organizations and specialists, to coeduct checks and investigations and give their expert opinions, and to be paid out of the specialists' expense accounts, estimated by the Committee; c) to introduce proposals into the ministries and departments, and to '
present the directors of enterprises and organisations under the Committee's cont rol with nuclear power safety regulations and norms which are oh11gstory for the implementation of the instructions to eliminate detected violations, and also to give the reasons and conditions leading to these violations; - -
d) to givd, to of ficials of enterprises and organisations controlled by the Committee, instructions for the elimination of deviatiosa from q's ,
solutions, violations of design or technological documents, and regulattene, noras and instructions dur!ng the construction and operation of these facili-ties, and during the manufacture, storage, installation, testing, operation ,
and repair of equipment, instruments and products controlled by the Casedttees y e) to give, to of ficials of enterprises and organisations controlled by the Committee, instructions which are obligatory to put a stop to work which is conducted in violation of nuclear power engineering safety regula- ,
tions, norms and instructions, and to seal up said work place or equiposats f) to prohibit enterprises and organisations from shipping Committae- .
controlled envioment in such cases where safety regulatione and mores are not being obser,ved, and where there are deviations from planning, destga and/or technblogical documentation; -
.]g t
I 69 .
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- 3) to take appropriate measures, to the extent of shutting deau ses& ear ,
power product. ion facilities should safety regulations and ee 1se so umsteegged, and for deviations free specifications, or design sad technola-4-=1 dassmeess ,
h) to bring, according to an established sequence, officials to aamamam**a- ,
tivo liability for violating nuclear power engineering safety resslatises,
-u noras or instructions;
- f 1) to sugAest to directors of ministries, departments, enterprises and
. orcanizations that, according to an established sequence, persons he relieved .,
i from their positions, or deprived, for a period of up to one year, of the ;-
right of technical leadership of operations, who: -
i
'l systematically violate the regulations and norms for safety in ==ehme p power facilities or the requirements of other standardizing documents; I .
l willingly do work, or allow equipment and foe 111 ties to be pet into j operation which has been shut dowaNon!the-instructions of abendies of tes Committee; !
? \
who have not taken training or passed an established sequence of emme- ~
l inations on nuclear power production safety regulations and norms; l T
[ j) to give head to probicas which are part of the sphere of competenes ,;
7 cf the Committee, and to listen to reports and information from representagives 4g of ministries and departments, and from directors of enterprises and orgamie- "
ations; G.
9 A j k) to participate in technical inquiries,which,are conducted acceedfag '
3 J to so established sequence, and which look into the circumstances and causee ,
of accidents at nuclear power production facilities and, for eaca* probima, '
which relates to the Coenittee's sphere of cos;scency, to carry est the ehti-gatory se16sions based on the findings of the inquiries;
[4S ,
-l ,,- .}
- 1) in the appropriate instances, to hand over materials to levest ,
agencies to make the guilty parties criminally responsible; .i , -
6.Q. , 2 ;i' m) . . . .
the need, shouldministries, to call for checkdepartments,enterprisesororganisationehavey) tests of equipment and materials, . check jt
- analyses of the working environment, and technical examination of equipeam.
%,U instruments and products; 7' .-
4 q*
n) to receive information f rom enterprises and organisations on the dents. M' of safety at nuclear power engineering facilities, on operational indienties. M., _-
i a
and on the causes of equionent breakdowns, and to receive, from directeesp., .
of enterprises, organizations and facilities, and from other officiale--englas- , .;; [,
ations of problems relating to the Committee's sphere of influsace, and eenen= , , t .
tific and technical reports and information by existing forms of reporttag.' 'p$ ' g j technical specifientions for facilities under the control of the Committee's y and technical pr,ocesses, all of which are necessary for purposes of familier- ,
e s
, Ization; i 4
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^
o) to check, within subordinate enterprises and organisatises, se the observance of the established order for allowing workers to west,en their certification, and on cheeks of their skill-levels, and en whether they hose appropriate documents; p) to take part in checking the knowledge level, regarding safety rege18-tions and norms, of supervisors and engineering and teeh=f a=1 methars of sek ordinate facilities, and to make spot checks of these pereceaal regesdias such knowledge; q) to determine, in secordance with interested ministries med departmante,
- the necessary additional scientific research, experiasotal design med p1mening operations, which are meant to improve the safety of suelear pesar faci 11 time, and for including them in the plans of corresponding or==ai==*8_ __ h 4=f d to an established order, and also to conclude agreements with metameHic rom arvh
- search, designing and planning organizations of the ministries and departments about carrying out these operations.
The rights stipulated in the above paragraph are granted to Goes* __
"_ T sgency officials to the extent determined by the Committee Chairmaa.
- 7. Cosatomenergonadsor is headed by a chairman appointed by the Usst Supreme Soviet, and between sessions, by the USSR Supreme Soviet Premi M =a, with subsequent presentation to the USSR Supreme Soviet for confirmatism. The Cosatomenergonadzor chairman has deputies, appointed by the USS Comesil of l
Ministers.
m the Cosatomenergonadsor chairman bears personal responsibility for the carrytas l _" out of the tasks and obligations entrusted to Cosatoneestgoemdsor, and be
- _- establishes the degree of responsibility for the Chairman's deputies and the l _
directors of the structural subdivisions of the Committee's central apparates,
- = in the leadership in the Committee's individual spheres of activity and for
_; the work of the organizations of the cosatomenergonadsor eyetas.
- When carryJug'out his duties, the Cosatamenergonadsor cheirosa enjoys the rights of a USSR minister. [s
- 8. The cosatomenergonadzor board is made up of the Coast--_ - =e-^^' ; hi ==".
i who is chairman of the board, deputies to the cosatomenere:- ' :: *hai===.
j sceording to position, and also other leading Cosatomenes;--- ' _:r westers.
9 r_ The Committee's board members are approved by the US$1 Comacil of Himisters.
~ At its regularly convened meetings, the Cosatamenergonadsor board leeks late "
3 the problems of improving state supervision of safety la nuclear pesar y, :-
7 tion, and other fundamental topics of the Committee's activity, diesessee
, questions of the practical leadership of organisations withis its Jeriadiaties.
checks on the implementation of resolutions, the selection and utilianties i of labor forces, plans for critical documents brought into the higher agencias, j as well as*th*e Committee's decrees, orders and instructions, and hears reports 5
~) 71 1
l
'.i l
~
j
.' m;" ] ,
- from the supervisors of the structural sebdivisions of the Cameistee's acessai apparatus and"organisations within its jurisdictions it hears set esob geneties within the sphere of its competence, and hears reports and saformation fees i etnistorial and departmental representatives, supervisors of schordiasse j enterprises, scientific research, planalog and designias and other argomise-
- tions and plant-menufacturers of equipment used in seclear power prodneties
- facilities.
- 9. Cosatomenergonadsor issues orders and instructions, and predeces disestices which are indispensable for the performance of the duties of the ochdiv nemme e
of the Committee's central apparatus, and the Goestamenergenadser system essee-1:stions. .
Within the bounds of its competence, Gosatonomersonadser issues decrees which are indispensable in the performance of the corresponding ministries, depart-l ments, enterprises and organisations.
(
In necessary cases, Gesatomenergonadsor isones decrees conjointly or la aseosts.n s j with other interested einistries and departments.
- 10. Cosatoesnergonadsor implements esasures for international coeparatise in the field of safety la nuclear power productioc, and notaemina, la MGM order, c-ications with the laternational Atomic Energy Assary and utsh State Committees for Safety in the Euclear power Industry of SET (W1 for Mutual Economic Assistancej eseher-mations and other seestries, esseosts negotiations, develops and presents proposals for scientific and techniest i
exchange, and presents plans for agreements with foreise commeries se q=ma*88==
which belong to the Committee's sphere of conpetence, sad aise sende v.- , ,-
the appropriate specialists abroad.
11 A scientific and technical council has been formed withia Geestamoserge-nadsor to exmaine questions included in the area of she Committee's esepr-tence, and also gives expert advice in the esselaation of cometractica pleno for nuclear power. production facilities and for analysis of the resalts of l their operationd * ,
l The personal make-up of the indicated councils and posittene se them are est hei. l l
orized by the USSR Council of Ministers. .g , j
, . e. .
I
- 12. The structure and number of workers comprising the central Geesteesserge- -; .
j nedror apparatus are authorized by the USSR Council of Nimisters. j j The regular time-table of the central cosatomenergonadsor apparatus is author- ;
- C' ized by the Committee chairman.
L i 13. Cosatomenergonadsor sets up, reorganises and liquidates regiumal assosies j.,
within its set limits for numbers of workers and budgetary allocattees, segh- - I
- orises positions on these agencies, and organises a network of moe-staff y ,,4 .
f inspectors, who work in positions authorized for them by the Committee. p.,, l
' I Cosatomenergonadsor works in close contact with other state supervisory agencies.
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- 14. CoestoneesserM=r 1seems as infeemstian be13atia (a (pse, , . .
which deals hath pueblems of safety la sosiser paese . """ e 3: ,
preventies, improving the esattering operatione of'esteediasta f Q, deals alee with the most laportant =ah8-= es esisees med gj $,.;f. .- {
y-and of leadies experience la these fields. ,
- 15. The enterprises and organizatises thish ase ender .F4 '
control, la order to create normal weeting ===d8*4- for Cementees '
/.
'l .
are obligated to provide the toepeaters withe [f ' g'
-z a . . .m a) the necessary documents (spesificattees, h1maprista.
.,7(
for operation, and for storage of eetput All gates State Stendeede'aing"dtIMr '[',i lafornattoo metorials) M.'Q., , ~.
1 u. . . -
. .n ,
b) accurate monitoring and teettag taetromenta and toets, pews".j-.. . ?,.
to conduct the tests and operations as - *=*ma with the carryisig/gestMsg,yf]' '
-clidij/
visory functions, and the necessary data from lahoestery c) the necessary special clothing, spesial Acessamr, and other emetyneeg::# - W 9.": *-'" t M '
protection egulpment ', t% * ?
. M ." v.;
d) utility roame, clerical'oervices, intercity talagheen and M , ',
'V p .. O' communication and transports **,g:.L v.@.s .
r 6. .. s *'
e) a family-sise living area from the besoing fa,eisee== ef tha' .. ",fjG
. L, / * ' f. .- 4 or from the ornanisation, other sources, la and, is the with accordance atosece the of liviesessaittees enesettes * ' ares, thisM of ehemId thkif.-f:
Councils of people's Derettas: ;
y p ..
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f) all forms of social welfare, cultural and =adia=1 servisies'eE with the corresponding category of wortere of the esterprias er 'j.pi..
'Y:2,
- .e '
- 3) the necessary scientific and tachasent infes==ti== and liteentums U
on the oeual terms.
Y.** . -
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- 16. Cosatomepassonadsor and its reglemal ap===8= pessoas the seel'ighetf the '
gh image of the State Embles and its designaties. $.15 ,y . ,,..4 --
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Re: F01A-86-335 APPENDIX H ASSOCIATED PRESS TELETYPE MESSAGE RECORDS MAINTAINED IN THE PDR UNDER THE ABOVE REQUEST NUMBER
- 1. 5/3/86 10:44EDT(1page)
- 2. 5/3/86 10:50 EDT (1 page)
- 3. 5/3/86 10:56EDT(1page)
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- 12. 5[9/86 10:35EDT(1page)
- 13. 5/9/86 11:16 EDT (1 pa9e) s ,, a#
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, ... RI i .,, 1 WORLD NUCLEAR REAX -
S0VIET huCLEAR h0HITORED POSSIILE CONTF:HINATION. THE FALLOUTRE6CTO AND 50HE .WITH
-SWEPT
. y;,
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IH' COMMUNIST ROMANIn:
'y.VEGETABLESANDAVOIDRURAL V-WASH FRUITS AND IN WEST GERMANY:
SOME FRESH 3AVARIAs HILK WAS F e CONTAHINATED FARHERS NOT FUT THEIR ANDC0WS ORDERED TO FASTURE. ' THAT. DEST -
N 1ARNS SWEDISH TODAIRY PREVENT FARHERS CONTAHIN ALSO NTERI Y
U
%ORASS.'FINNSANDNORWEGIA D0FEASTERNEUROPEANDTOTAKEOT IN' COPENHAGEN -
- ' ; N0 SPECIAL PRECAUTIONS APPEARED 1INFANTSOUTSIDETHES0VIETUNION. s CHILDREN.0R 9
'x
? AND ErTSTERN
. RADIATION LEVELS 300STED 3Y THE DISASTER.
R0HANIA AS
' p; RADIATION SFAWNE3 3Y TH
' UKRAINE POSED N0 HEALTH THREAT. N THE OW-LEVEL;
WE HAD 400 CALLS IN THE LAST THREE HOURS 230MMERMUThe -
V Y.
70FFENEACHr A SP0KESMAN WHICH IS COORDINATING FOR THE WEST GERP. .s y RADIATION
" HOST OF",HE THER SAID SAY THEY ARE' REPORTSONRADIniiONLEV ON FRIDAY. 8!THEY WORRIE
.,UEGETrT3LES FROH THEIR GARDENS THE . ALS ',
p.PEOPLE ARE WORRIED." IF THEIR CHILDREN CAN GO OUT 4-THERE IS CONCERN ,
BUT NO EVIDENCE OF PANIC.
WE ARE NATURALLY QUITE WORRIED," , 31s A SAID HIK '
' POSTAL' CLERK IN STOCKHOLH
,ANYTHING LIKE THAT.'
j i
i
.LMONDAY,SINCECLOUDS OWEDEN FIRST DETECTED OF RADIGACTIVE DUsi FRO SOUTHWESTERN
' i.EVELS HAVE BEEN S0VIET DROPPINGUNIONINHAVE .
SCAND '-DR*
CARRIED;THE FALLOUT'INTO R0HANIA, HUNGARY: H AUSTRIA'WAS, EXPECTED TO PUSH IT BACK WEEKEND. * * '
IS 7 TO WIN 1.0NDON: .
REMNANTS IUT DTD NOT 300ST RADIATION LEVE OF THE'RADIGACTIV ND' FRIDAY 1ROADCAST A STEADY STREAH:8[.
3, O l
P.1013 ' STAYING UNWASHED FRUIT AND VEGEIAiLES. OUTD0 ORS FOR TO EAT LONG E TO .
AP-WX-05-03-86 C .
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.g . . ,,-,.3 -. . C~:.Q RI SWEDEN-RADIATION STOCXHOLH SWEDEN (AP) -- 0FFICIALS ACROSS SCANDINAVIA HAVE REC 0HilENDED NEW PRECAUTIONS 3E TAKEN AGAINST RADIATION SP
. NUCLEAR DISASTER IN THE S0VIET. UNION, IUT SAY THE RADI0 ACTIVITY ISg NOT
-HIGH EN0 UGH 10 3E A HEAliH RISK. H
' TIN GENERALS THE LEVELS ARE VERY L0k, AhD WITH OUR REC 0HMENDATIONS -
WE AIH AT KEEPING THEM LOW FOR THE FUTURE ' GUNNAR SENG SWEDEN'S NATIONAL RADIATION PROTECTION INSTITUTE, SAID FRIDAY.
IN'0ENERAls 3ENGTSSON SAID, RADIATION IN THE AIR WAS CLOSE i0.HORMAL' LEVELS, 30T kE STILL HAVE TO COPE iilTH WHAT IS LYING ON THE GROUND."
THE INFACT OF THE REACTOR FIRE AT THE CHERNOBYL NUCLEAR PO 1 STATION IN THE UKRAINE APPEARED CERTAIN TO AFFECT & SCA WEEK $i AND 141NDS THAT HAD DRIVEN FALLOUT AWAY.FOR A.e... FEW D
< EXPECTED TO SWING BACK TO'THE NORDIC COUNTRIES ON SUND '
SWEDISH DAIRY FARHERS WERE ADVISED TO HOLD C0WS IN THEIR - . W IARNS'TO PREVENT CONTANINATION OF HILK EY RADIATION-DUSTED ? F
.0RASS. FINNS AND NORWEGIANS WERE TOLD NOT TO TRAVEL TO AFFE
- 0F EASTERN EUROPE AND TO TAKE OTHER LOW-SCALE PRECAUTIONS.,
a.(
IN'COPENHAGENs THE WORLD HEALTH ORGANIZATION'S EU N0'SPECIAL PRECAUTIONS APPEARED NEEDED FOR PREGNANT WOMEN, CHILDREN OR
' INFANTS OUTSIDE THE SOVIET UNION. - . .
ALTHOUGHOFFICIALSSTRESSEDTHEREHEREONLYHINIMALDANGERS NORDIC COUNTRIES AUTHORITIES SAID ThAT IN LESS THAN A WEEK THEY'HAD FOUND'THE RADI0 ACTIVE IS0 TOPE IODINE 131 IN 12 FEOPLE 372 FINNS WHO WERE EVACUATED FROH KIEUs 80 HILES FROH T THE ISOTOPE DOES NOT OCCUR IN NATURE AND IS KNOWN TO CAUSE CANCER;0F i
'JHE THYR 0ID GLAND. THE DISEASE CAN 3E CURED IF TREATED EARLY.
g ENUIRONHENTAL ACTIVISTS IN SWEDEN FRIDAY CLAIHED THA gAREAS1HERERADIATIONWASis000TIMESHIGHERTHANNORHAL,ALTHOUGH 9; hAUTHORITIESHADDIFFERENTREADINGS. Mpd P
IENG1SSON SAID HIS NATIONAL RADIATION INSTITUTE H
?WHERE' LEVELS WERE 200 TIHES THE NORH. EVEN AT THAT LEVEL, HE SAID, AN W
'EFFECs.
EXPECTANT NOTHER COULD STAY THROUGHOUT HER FREGNANC '
DANISH OFFICIALS SAID RADIATION LEVELS liERE VIRIUALLY NORHAL AGA FINNISH AUTHORIT'ES SAID LEVELS WERE CONTINUING 70 DECLINE BUT II
- 4 S(AP-WX-05-03-861050EDTTAKE WEEKS BEFORE ' %.$l[.
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FRANKFURT PLANT ~ DISASTER HAS 0WS CONTAHIHaiE INDOORS. -AN '
RECONHENDED R83IATION LEVELS ON FRIDAY TO FARMERS THATREH61 THEY l PARTS'0F WEST GERHANY:
CHERN03YL IN THE UKRAINE:
AND FOR THE FIRST INT WHERE THEY~ f D
- dei
/,COUL3~3EC0HE AND WESTERN EALTH D6HGER00S FOR H PRRTS OF THE Md C ERMANY $
l 1
A "IH THE NEXT FEW ORDERED DESTROYED.
DAYS LE Sy;CA !
?L. THATCRITIC 6L RADI0nCTIVITY LEVELS:"
ens THE HEAD OF n SPE SRID ERICH OF S FR 03ERHA 00VERNMENT TASK FORCE BAVARIR SETFOU!!D UP PES
FALLOUT SP6WNED BY THE R C0WS; I
'r4 10DIHE MILK TO131. CONTAIN THE GOVERNH fi300T .i$
D e fWel; y OUT NATURE TO PASTURE.8HD ISFRESH KNOWN HILKTO USURLLYCAU
- s. TO STOP NURSING 'M6 i:
CONCENTRATES IODINE.03ERHR CHILDREN.
Q, R RnDIGACTIVE J F
- THE HEALTH HINISTRY ORDERED A .
7d 1
SOVIET UNION RND EASTERN ICLES END PASSE EUR' l
i CONTANINATION ADI0 BEFORE O ROMsHIRs WHERE
~
ACTIVITY CE '
4 9 FROM EBSTERN EUROPE
' THE CLOUD SPEHED BYSTERNEURDEESHO 3YL.
THE RERCT ,
A
- d g;%
HORE THRN 150 CARS AND TRUC l 4 THAN NORi1RL R6DI0 ACTIVITY: EASTERN EURO?E'WE N DECONTAn! NATION.
- $ W 3EING CHECKED WITH SPECI RED RADI0 ACTIV
/
-c4 GETTING OFF THEIR PLANES.
~ THE NORTHERS FORTS ~
J.s 1"
$y,dLEnUING THE VESSE 3
o '- '
- ~~ .?. :
1 M CLOTHES'0F.SERMEN i'ty -'
CHECKED.
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4 k o d .it:: R M T E W '~' ' % '~? C? D ' ? \ N' N '. k. Y Y $
,g HE SAID A3NOR!iAL uCCURRENCES, ThE HOST SIGHarICANT EVENTS, DID RISE FR0!i FIVE IN 19Si TO 10 IN 19S4 6ND NIhE LAST YEAR. BUT HE nDDED, '!AT
' .THE SE!iE TIME, THERE ARE !!0RE REACIORS IN OPERATION.' THERE WERE 6S NUCLEAR PLANTS IN 1979. CURRENTLY 100 PLANTS h0LD OPERATING
' IfrCAll:ING FOR A PH8SE-00T OF NUCLEAR GENERATORS, CRITIC 8L HnSS CITED'NRC TESTIliONY THAT THERE IS A 45 PERCENT CHENCE T O
- .JilELTDOW!! AT A C0!lliERClel U.S. REACTOR BEFORE THE YEAR 2000.
~
HEDLIN SAID THE TESTIlt0NY GIVEN LAST YEAR EEFORE ft C0llGRES PANEli REFERRED TO A THI-TYPE ACCIDENT IN kHICH HOST RADI0nCTIVE RELEASE 3 RRE C0!1 FINED TO THE CONTAIN!:ENT IUILDING SURROUND -
REACTOR.
QIIDTING HRC CHAIRii6N NUHZIO PALLADIN0s HE SAID THE E ' INDIVIDUALS WOULD~ 3E LOWER THAN THE CHANCE OF A HELTDO
.i '0RDERS OF ttE0NITUDE" 3ECAUSE CONTAINHENT ST I;' 0FFSITE CONSEQUENCES IN ALL BUT A FR6CTION OF CORE-HELT ACCID ItrITS REPORT TO ThE HARKEY SU300HHITTEE, THE NRC SAID THE JUNE 9,
19S5 DAVIS-3 ESSE ACCIDENT INVOLVED THE BREAKD0HN'0F THE AUXILLARY FEEDUATER PUtiPS llECESSARY TO C00L THE huCLEAR.C0 tHAVE RESul.TED IN ' FUEL DANAGE: IRE 6K 0F PRINARY SYSTE5, SIGNIFICANT. -
>< RELEASE OF RADI0 ACTIVITY.
[ IEFORE AN E!!ERGENCY MATER PUHP COULD BE STARTED AT THE DnVIS-BESSE
^ REACTDRs 'THE PLANT'S TWO STEAH GENERATORS HAD ESSEN
' EEFORE FEEDWATER FROH 6NY SOURCE SECEliE nV81LABLE TO THEH,' THE REPOR SAI3. -
IfriSS0 THE NRC HAD DIRECTED TOLED0 EDISON: THE PLANT'S OPERETGR, T TO REPLACE ONE OF THE TWO STEAH-DRIVEN ENGINES THAT RAN^ T EAUXILIARY FEEDWATER PuliPS WITH AN ENGINE POWERED B
'S0URCE. THE ORDER HAD NOT 3EEN CARRIED OUT WHEN THE ACCID .
THE'.NRC
' REPORT ALSO INCLUDED ACCOUNTS OF:
- g. -- THE LOSS OF ELECTRICAL POWER AND A " SEVERE kRTER HAMMER' O -
f SHUDDE8Ili0 unTER PIPES THAT CAUSED A STEAM LEAK AND DAHSGED 2 AT THE SRH ON0FRE UNIT i PLANT HERR SAN CLEMENTE: CALIF.i.0N NOV. 21,
).#'1935.'STEAH GENERATOR FEEDunTER WAS LOST FOR THREE THE C0HNISSION SAID FIVE SAFETY-REL6TED FEEDUATER SYSTEH C
.. VALVE'i DEGRADED TO THE P0lNT OF IN0PERASILITY DURING A PERI o; THAN A YEAR WITHOUT DETECTION. THE PLANT IS CLOSED TEMPORA .
- AN UNUSUAL POWER SURGE 6T THE VIRGIL C. SUMMER NUCLEAR S UNIT 1 IN 3R08D RIVER S.C. THAT CAUSED THE PL6NT TO AUiGHATICALLY HSHUT 10uN WHILE IT WAS 3EING STARTED UP BY OPERATORS.
5PROCEDUREDEFICIENCIESWERERESPONSIBLEFORTHEFEB. 28, 1985 EVENT, hTHENRCSAID. ' ,
.9 -- THE FAILURE OF NINE OF 12 PRESSURE TRANSilITTERS THAT WAS S DISCOVERED AUG. 7: 1985 AT THE HAINE YANKEE AT0t1IC POWERi P I!ATHs~liAINE. THE TRANSHITTERS THAT HONITOR THE PRESSUR
@0ENERATORSWEREINOPERABLEBECAUSEROOTV6LVESHADAPPARENTLYB ...
3CLOSEDFORHORETHANAYEAR.
~'
-- THE FAILURE OF THREE HAIN STEAH ISOLATION VALUES TO CLOS "AT THE BRUNSulCK UNIT 2 ON SEPT. 27, itS5. THERE NAS NO DANGER BECAU f THE PLANT NEAR SOUTHPORT H.C.
HAD 3EEN SHUT DOWN. BUT THE NRC NOTED THE INCIDENT INDICATED A C0HHON E0DE F6ILURE 0F ThE SYSTEF. THAT PREVENTS THE ESCAPE OF RADIATION.
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PERING (AP) - .TNE. GOVERNMENT EXPRESSE1 CONCERN TODAY ABOUT THE '
SOUIET NUCLEAR ACCIDENT AND SAID IT WAS HORITORING THEJATHOSPHERE FOR - .
RADIATION. ,
lie EXPRESS OUR CONCERN OVER THE SERIOUS ACCIDENT THRT.0CCURRED fit-THE CHERN0EYL NUCLEAR POWER' STATION: CAUSING CRSUALTIES AND POLLUTION' 0F THE ENVIRONHENTs find OUR SYHPATHIES AND SOLICI.TUDE TO THE INJURED AND FHNILY HEHEERS OF THE DECERSEBi'5 THE FOREIGN HINISTRY SAID IN 8 STATEMENT. - g .
UUR DEPARTHENT CONCERNED IS KEEPING A CLOSE NATCH ON THE IMPACT THE RECIDENT HAY HAVE ON THE ATHOSPHERIC ENVIRONMENT OVER CHIN 83 58IT.
SHID.
THE ACCIDENT: NHICH SOVIET OFFICIRLS HSVE SRID OCCURRED APRIL-26 HT THE HDCLEBR POWER PLRNT 80 HILES NORTH OF KIEV IN THE UKRRINEs SENT fi CLOUD'0F RBDISTION OVER HUCH OF EUROPE. IN EUROPEr.SEVERAL' COUNTRIES TOLD THEIR CITIZENS TO T8KE. PRECAUTIONS'AGAINST RADIATION.
CHIH8 H6S NO OPERATING NUCLEAR. POWER PLANTS BUT-TN0 BRE UNDER ,
CONSTRUCTION ST DRYR 3RY IN GUSNGDON6 PROVINCE AND QINSHAN IN 2HEJIANG
' PROVINCE. TWO OTHERS BRE PLANNED BY THE END OF THE CENTURY.
. THE PROJECT AT QINSHAN NRS ORIGINALLY K ANNED FOR R SITE NEfiR SHANGHBIs EUT 8FTER THE 1979 NUCLEAR ACCIDENT AT.THREE MILE ISLfiND IN PENNS7LUSNISs THE CHINESE LEADERSHIP ORDERED IT HOVEB TO RURfil HnIYBN COUNTY. .
8N'0FFICIRL ST THE 15506-MEGAWATT CHINESE-DESIGNED PLftNT RECENTL'l SAID MANY HfilYAN RESIDENTS ARE UNEASY.ABOUT LIVING NEHR THE PLANTS WHICH'TS SCHEDULED TO BEGIN OPERATING IN 1989.. '
FRENCH AND 3RITISH COMPSNIES fire BUILDING THE 15800-MEGRWfiTT DRYA ERY PERNTs WHICH IS SCHEDULED FOR COMPLETION BY 1991 BND WILL PROVIDE ELECTRICITY TO HONG KONG. '
WESTERN DIPLOHATS IN PEKING PREDICTED THE CHERNOBYL fiCCIDENT
'PROIRELY WOULD HnVE LITTLE LONG TElH EFFECT ON CHIN 8'S NUCLEfRi-POWER INDUSTRY: WHICH H8S ORDERED HUCH OF ITS EQUIPMENT FROM WESTERN COUNTRIES.
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KIEUs U.S.S.R. (AP).-- AN INTERNATIONAL ATOMIC ENERGY AGENCY #
.0FFICIAL SAI3 TOMY THAT THE FIRE AT THE CHERN0BYL NUCLEAR REACTOR MH PDT GUT. THE MYOR OF KIEY 4Ali A QUARTER-MILLION CHIL3REN WILL -
LEAYE' SCHOOL EARLY TNIS YEAR 3ECAUSE OF THE DEURSTATING ACCIDENT', -
TM AGENCY OFFICIALS NORRIS ROSENs TOLE A NEWS CONFERENCE IN MOSCON ',,'. .
' THAT AN A3JACENT REACTOR HT THE UKRAINIAN FACILITY SUFFERED SO .
38 MAGE 307 ITS COOLING SYSTEN NAS HORKING M3 THERE HS NO BANGER
' 8 ECON 3 R UCTOR N00L3 RELEASE RA3IATION. : e.
XIEY NAYOR YALENTIN SOURSKY SAID SCHOOLS ATTENDED SY A ' . l.9 i
90ARTER-MILLION OF THE CITY'S CHILDREN. NILL CLOSE E M LY THIS YEAR, 7'#" *
.MCAUSE OF THE PONER PLANT ACCIDENT. HE SAIB THE NOUE WAS NOT AN ENER0ENCY NEASURE.- - -
"NE ARE SINPLY A3YANCING THE NORMAL SCHOOL HOLISAY'A LITTLE BITS'8.; ' -
SohASKY TOL3 A 6'R00P OF FOREIGN REPORTERS DURING A VISIT- ARRANEED
,THE 80VIET FOREIGN NINISTRY. -
i
- "R MRAINIAN HEALTH NINISTER ANATOLY ROMMENK0 WAS QuGTED EARLIER.89
~
SAYIM GN RIEU RDIO.THAT SCHOOL CHILEREN liGULB EE MOUED 00T GF THE .;. ;[ .
AREA AS A PRECAUTION. KIEVs THE NATION'S THIRL-LAREEST CITYs Is 86 ~
MILES SOUTH OF THE 3AH 0E3 REACTOR. ,
AT THE NOSCON NENS CONFERENGEs ROSEN SAIB NORKERS NERE TRYING 10 ,
, SEAL GFF THE NO. 4 REACTOR AT THE CHERN0EYL FRCILITY WHERE A CHEMICAL EXPLOSION OCCURRED APRIL 26,. SETTING 0FF A FIRE AND SPENING A
'RA3IGACTIVE CLOU3 OVER . EUROPE. .
!'THE RIN IS TO ENCASE THE WHOLE FOURTH UNIT IN CONCRETE ANL HORK
.M8 IEGUN TG PLACE A CONCRETE FOUHATION UNBER THE REACTOR:" HE SAID.' .
- UKRRINIAN PREMIER ALEXANDER LYASHK0 HM TOLD 'NESTERN JOURNALISTS XIEU ON THURSBAY TMT CRENS STILL NERE TRYING TO PUT GUT THE REACTO
. FIRE.'THE IIRECTdR OF THE U.N.-AFFILIATED INTERNATIONAL ATOMIC ENERGY '
AGENCY, HANS 3LIX .FLEN OYER THE REACTOR THURS3RY MB SAID ON S0ilIET -
TELEUISION TNAT SNOKE WAS C.0NING FROM THE FACILITY.
. 30T ROSEN SAID TOBAY 'THE FIRE IS OUT." HE SAID HIS INFORMATION -
CHE FROM SOUIET OFFICIALS AND OBSERYSTIONS OF A TEM FROM THE VIEnas
' AUSTRIA-3ASEE NUCLEAR WATCH 3.00 AGENCY. , ,
AP-NX-85-09-64 8901EDT '
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< CNERW63YL FIAE i NOSC04 (AP) -- AN INTERNATIONAL ATOMIC ENERGY AGENCY OFFIQIRL S413 THE FIRE AT CHERN03YL NUCLEAR PCHER PLMT'S NO. 4 REACTOR H -
EXTIN6UISHGs AN3 SAIR THE REACTOR ES BEING ENCASED IN CONCRET -
NOARIS ROSENs 3IRECTOR OF THE U.Ha-AFFILIATED AGENCY'S' D "
NHCLEAR SAFETY: ALSO 8813 THERE iMS SOME FIRE BANAGE TO .THE PLA A3JACHT N0. 3 REACTOR: 30T THAT ITS COOLING SYSTEM WAS WORKING .
NE SAll THEi3ANAGE POSED NO ENYIRONMENTAL DR HEALTH THREATS.
ROSEN SAIB HIS
SUMMARY
OF THE T
' ACCIDENT BT ' HE <1 DKR PONER~ PLANT NHICH HE GAYE TO REPORTERS EURING A NEWS CONFERBCEs WAS! -
MSD'ON TALXS WITH S0YIET OFFICIALS AS WELL AS AN AGENCY TEM'S -
' l 88SERVATIONS. '
' IAEA IIRECTOR HANS ELIX TOL3 THE NEWS CONFERENCE AT THE .. S0Y FOREIGN MINISTRY'S PRESS CENTER TMT'HE AB THE OTHER AGENCY O LOOKIM INTO THE APRIL 26 ACCIBEKT HAD FORMED R " PRELIMIN
,,388H GN TALKS NITN SOVIET OFFICIAL'S.
3LIX S813 THE SOYIETS HAYE' AGREED TO PROUIDE 3RILY READINGS RA31ATION LEVELS BEGINNING TOBAY FROM A HONITORING.STfiTION 371/2 NILES .;- '
. FROM THE POWER STATION, AS NELL AS FR0h SIX OTHER STATIONS ALOWS TH -
SOUIET UNION'S HESTERN BORDER: FROM LENINGRAB TO THE BLRCK S 3LIX SAll'0N SOVIET TELEVISION- THRSLAY NIGHT AFTER FLYING DV
' PLMT SITE THAT SMOKE WAS STILL COMING FROM THE NO. 4 RERC
, "THE FIRE IS OUTS" ROSEN SAID TODAY.
HE'SHIE INVESTIGATIN0'0FFICIALS HAD' "GNLY HYPOTHESES" DW W ACCIAENT OCCURR'O. HE SAID RECORDS RECOVEREE FROM THE RER '
' ~ -
'290N HERE N UER STU3Y.
ROSH 8813 ALL 204 PEOPLE INJURED IN THE ACCIDENT HRD BEEN
' N0SCON FOR TREATNENT, M3 THAT NOST OF THE YICTIMS WERE FIREFIGHTERS. .
- "'. .RGSEN SA H INJURIES HAVE 3EEN CLASSIFIED IN FOU l '
PEOPLE IN SDIGUS. CONDITION AFTER SUFFERING " FOURTH-DEGR i EXPOSURE.' HE III NOT PROYIEE FIGURES FOR THE ANGUNT OF RAD
,' NNICN EACH OROuP WAS EXPOSE 3. .-
THE S0VIETS ARE TRYING-TO SEAL THE REACTOR IN CONCRETE, HE SHIB.
.e "THE AIN IS TO ENCESE THE NHOLE FOURTH' UNIT IN CONCRETE AND HAS IEGUN TO PLACE A CONCR.ETE FOUNBATION UNDER ~
THE R
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STOCXHOLNs SWGEN (AP) -- NUCLEM EXPIRTS' 6.'iE CONCEANEIL TET A. -
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SECONI REACTOR AT THE. STRICKEN SOVIET CHERNOBYL NUCILAR PLANT Es 3 MAGE 3 IN THE"EXPLOSISN NURLY 'IWO MEKS AG0: SWEUiH OFFICIALS SHIB ' '
1838Y. .
6
- SVEN GUSTAFSSON OF:7HE SWE3ISH NUCLEAR INSPECTION 30ARD SRID TET ~
C8NCERN CENTERD ON CMEAN0BYL5S NO. 3 RERCTORi THE PRRTNER REACTOR 70 .
TM GNE HOSE 3ESTRUCT10N CONTINUES TO SEND RADI0BCTIYlTV. INTO THE AIR. ' -
g GBSTAFSSON SAI) THAT. 88JU.%ING FROM TH$' INFORNRTION 89THEREB, IT .
SEENS3AT THE THIRB RE8CTOR 3S UNDER CONTROL.88 EUT HE SAID THAT IT C: '
MS FEL7 THE POSS.IIII.ITY OF 3dMRGE.C'0ULD WOT BE EXCLUDED BECRUSE THE . .
STRICKEN NO. 4 REACTOR HSS NEAR3Y AND 55HH6T. MS HPPINING THERE ES OF .
8 UERY UIOLENT NATURE.88 1 _
S001ET OFFICIALS HAYE 3ENID EBRLIH SPECULRTION BY WESTERM EXPERTS E
TMT A SECONI REACTOR NAS HNAGED I}', THE APRIL'26 EXPLDSION AG 7 IRE AT '
E THE CHERN03YL PONER PLANT 88 NILES 10RTH OF T!{E UKRAINIAN CAPITAL GF 1
.KIEU. . .
./*. ..
HONEVER: QuSTRFSSON SAI) TMT SEDISH EXPERTS HD STUBIED S0VIET .
I STATENENTS AND EXCHNGED INFORMTION WITH RMERICANi BRITISH RNB WEST -
GERMN NUCLEAR EXPERTS IN THE COURSE OF. CONCLUBING THERE COULD BE a - !f PR03LEN HITH THE SECOND CHERN031L REACTOR. .
. LARS H0 0 ERG DEPUTY HERD OF SWEDENS NUCLEAR POWER INSFECTIUM
- 388Ris MS GUGTE3 AS SAYINGi1N BN ~ INTERVIEli WITH SEDEN5S i.HRGEST . -
WORNING.NEHSFRFER: MGENS NYHETER: T ET REDIP. TION PROTECTIO!! EX?ERTS
'M5 NUCLEAR POWER INSPECTORS HEETING IN PRRIS TODRY WOULD BISCUSS THE '
-RISX.0F ANOTHER RERCTOR 3REARDOWN AT CHERNOBYL.
THE PARIS NEETING WILL .1MOLVE OFFICIRLS AB EXPERTS FROM COUNTRIES MITHIN THE OR6RNI28 TION FOR ECONOMIC COOPERATION MD DEVELOFNENT. -
HOGIERG MAS QUOTED AS SRVING THERE RSS SFECULRTION THAT THE N0, 3 REACTOR HIGHT NOT HAVE SUFFICIENTLY C00LE3 9FTER THE CHERNOBYL FACILITY ,- ~
NAS SHUT BONN FOLLOWING THE ACCIDENT RT NO. 4.
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' MCLEAR SAFETY ' ANE MAS AMITING A REPLY . ., FROR THE -
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' CNERNSYL IISASTEA OCCURRE3.' JAAES R. SHEA, 3! RECT .
THRSHY HE IS STILL HOPES THE VISIT c . ..MY THE ACCIMNT IS'1ETTER UN3 ERST 00D TMT THE SOYIET '"
PROPOSALS" SHEA 10L3 THE SENATE.00VERNMENT :AFFA
- EERGYe NDCLEAR PHOLIFERATION AND GOVERNMENT PROCESSE C
- MT REPORTS IN THE SOUIET UNION ON THURSHY SA '
C8RRIO HIGHER LEVELS OF, RHIRTION FROM THE HRNING REACTOR -
. T THE utRAINIAN CAPITAL OF 2.4 MILLION PEOPLE 80 MILES SO
'CNERN03YL PLANT. .
. HEALTH.PRECEUTIONS kERE IMPO..ED IN THE CITY S ' '
g3An :
ERE REPORTE3 FLEEING.
" UKRAINIAN PREMIER ALEXANDER LYASHK0 TOLD A V
.THE FIRST ALLONES.INTO THE UKRAINE SINCE THE ACCIDE REPORTERS J
18E, REACTOR' FIRE US " PRACTICALLY STOPPEL" AWB RADIAT . Je .(
RITN A TEHENCY 30NNMR3." -
~
~ OFFICIALLY'THE 3ESTH TOLL IS TW0s BUT THE OFFIC '
AGENCY TANJUG SAIB IN A 31SPATCH FROM M.0SCON
- THEiNRC STAFF WAS f,EYELOPING A DRAFT' AGREE
- IN A KIEY . HOSPITAL.ACCOR3ING TO SHEA
. NUCLEAR SAFETY C0CPERATION .WITH THE SOU ALL NORK CAME TO A STOP IN 1979 AS PART OF THE U 869. INST THE S0YIET INVASION OF AF0HANISTAN. -
STRE EFFORT LAY 30RMNT UNTIL THE,NRC STAFF HSKED TO , ,
' UNION: NE SAII.
NORI 0F'THE PROPOSEB VISIT CM E AS FEDERAL OFF IETECTEI MIMIE LEVEL.S OF AIR 30RNE RADIORCTIVIT -
- .FIRST' TIRE IN THE UNITE 3 STATES. THE READINGS 'W
~
- NESTERN U.S. CITIES.
NONITORING STATIONS THIS WEEK BETECTED LEVELS PIC0 CURIES PER NYO., .CU3IC NETER MOF SR.sYARIOUS RADI0 CHEYENNE, A 0 RICHLANB: F DERAL OFFICIALS
.. -- AT M NYER
/ SAI)."THE ENVIRONMENIAL PROTECTION AGENCY SAI ,
- 5. REPRESENT A THREAT TO AREA RESIDENTS. '
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NE NI5!aTM $213 IN AN-MTICLE PURISHD-183AY. .:
TM ARTICLE IN THE OFFICIAL PRAUBA UKRRINY NEWSPAPER BY : AN8TOLY !
30E M R0 E 80 REPEATE3 RECO ME H ATIONS THAT PEOPLE M8SH AELL, NATER 30M 1MIR $TREETS A M YAR3S AN3' KEEP CHIL3REN IN300RS'TO MOIB ANY "
.t3NTRIMTIM FRON RA31080TIVITV' RELEASH 3Y THE APRIL 2$ HPLOS, ION BMi -
'?:
. FIRE AT TE !AT8NIC RONE4 PLANT. ' J3t' 1E SOUIETS HME 1RI3 TWO P.EOPLE HERE KILLE3 AND NORE THM 244- '
INM3 IN TNE 8CCIMNT 3ELIEVO TO THE WORST IN WISTORY IN0LUIN8 A ' J WCLEAR REACTOR.- .
p'! .::
' 4:
. snygE SITNTIM HAS MRKERY IMPROYEl SINCE MY LAST AllRE8S$"
Mummme mil IN. TOMY'S ARTICLE. "THE LEYEL OF 3ACK6ROUND RABIATION,3.1 -
..Il GRWALLY FRLIM. AT PRESENT IT IS IN THE LIMIT OF. TM N0tN8 .d
.. REtemEMER BY MTIONAL AR3 INTERNATI0 MAL GRGANI2ATIONS AW3
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. REPRESENT 4 3 ANGER TO THE ME ETH OF THE POPULATION. INCLUDING
- - l', - -
MIL 30EE.n . .
Y TE PRMM UKRAINY ARTICLES H0HEYER, SID NOT NAKE CLEAR HETHER
.?-
ROMEDES NAS REFERRINS TQ'THE CHERN0HL SITES MICH HAS MG USC58TE3,.04 THE CITY OF KIEV ITSELF 60 MILESnT4 THE SOUTH. '$p
't GPTNGESM Ye UKRAINIAN PREMIER ALEXANDER LYASHKG TOL3 A SROUP
.' VISITIM REPORTEtt THAT.A FIRE AT THE FOUR-REACTOR .
t .- POM STILL SNGL M RING. ': -
"TR TEMPERATURE OF THE REACTOR HAS 60NE BONN TO 396 NGREE THE ,
l .
CELSBS (572 M8REES FAHRENHEIT)s" LYASHKQ SRIS. s'THIS NEANS Tl
'c350 RIES H8$ PRACTICRLY STSPPH. THE RABIATION IS STABLE 'WITH
- '*TERMCY 30lMIGRR." .
i . . THE'
- - 0FFICIES. HONEVER, 413 NOT PROYIDE PRECISE REASINGS, . '.-
T W Ys THE NAYOR 0F'.KIEY TOLB THE REPORTERS UISITING HIS CITY, THE - - ..
. THIRFLARGEST IN TM 50YIET UNIONr THAT:254:let CHILDREN MILL LERVE SCOBM.EARLY THIS YEM BECHUSE OF THE CHERNORYI. ACCIBERTs 3DT SAll THE '
' M CISIM M t NOT M ENER6 H CY MEASURE.
l '
. "EE ABE SIMPLY 43Y8MC-INS-THE NORMAI SCf04 HOLIDAY A LITTLE BII:" '. -
- GALESTIN 96MSKY S813. '
. r TNE SELECTD GRO11P GF HESTERN M3 E8sT .3 Luc'CORRESPONSENTS TAKEN TO ,
Y EM9 780M THE CITY IN A HOLIDAY N003 HITH THE 8PPRGACH OF THE AHUA
- UICTERY 38Y C8MEMORATISH OF THE WORL3 WAR II YICTORY OYER B -
- M CELEM4TE3cT03AY. '
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11EY: U.S.S.R, (AP) - AN INTERNATIONAL ATONIC ENERBY AGENCY '
IFFICTAL 8A13 TOMY THAT THE FIRE' AT THE CHERN0lVL NUCLEAR REACTOR HAS'"^-;
EED PBT GUT. TH( MYOR OF KIEU. SAI3 A QUARTER-MILLION CHILDREN HILL
- LHUE' SCHOOL.EARLY THIS YEAR 3ECAUSE OF THE BEVASTATING ACCIDENT.;'
TM AGENCY OFFICIALS MORRIS RGSENs TOLD A NENS CONFERENCE IN MOSCOE '.' l JTNT W ANflCENT REACTOR AT THE UXRAINIAN ' FACILITY NAS NOT DAMBE8 BY
.TM FIRE MS M8 NOT IN 3 ANGER 0F RELEASING RABIATION, ~
'EIR MYOR VALENTIN SOURSKY Saf3 SCHOOLS ATTENBE3 BY A
. '888RTER-MILLION OF THE CITY 8.S CHIL3REN HILL CLOSE NAY 15e SEYERAL H s~ EsALYr MCaOSE OF THE POER PLANT ACCIBENT. HE SAIB THE HOUE HRS NOT AN.
BERENCY MER$URE.
- . f.
t'.,
'"E ARE SIMPLY AMANCING THE NORMAL SCHOOL HOLI3AY A LITTLE BITS" W i 3,.'
30ERSEY TOL3 A GROUP OF FOREIGN REPORTERS. i MIGINIS ERTH NINISTER ANATOLY ROMNENK0 MS 900TE3 EARLIER AS ? ?' '
2.$$Y15 ON MIEY RREIS THAT SCHOOL CHILDREN NOUL3 3E NOUED QUT OF THE
. 8RES 38.8 PRECAUTION. KIEYs THE NATION'S THIR3-LARGEST CITYs IS 88 5
. RILES $MTM 0F Tile' WCLEAR PLANT.
MIAINIAN PREMIER REXAMER LYASHK0 TOL3 REPORTERS THURSBAY THRT- }.:
.INTNRITIES 313 NOT ORER THE EJOR PART OF THE EYACURTION UNTIL SIX
-MYS WTER;TE ACCI3ENTs ANI WAITED FOR TNG BAYS TO INFORM N05 COW OF .
.TNE FEL SCOPE OF THE HORST 31SASTER IN THE HISTORY OF NUCLEAR POWER BT*TME N0SCOM E NS CONFERENCE: ROSEN SAI3 NORKERS NERE TRYING TO -
SEE WF TE NO. 4 REACTOR AT THE CHERH03YL FACILITY HHERE A CHEMICAL E3PLOSION OCCURRE3 APRIL 26: SETTING OFF A FIRE AD SPENING A
.an314ecTIVE.CL00 OYER EUROPE.
"THE AIN IS TO ENCASE THE NHOLE. FOURTH UNIT IN CONCRETE AH ~ ' NO s HRS 3EGM TO PLACE A' CONCRETE FOUH3RTION UNDER THE REACTOR:" HE .
' SAID
-;. LYRSR O NA3 SAID THURS3AY THAT CRENS STILL WERE TRYING TO PUT 007 -
a TM REACTOR FIRE. THE IIRECTOR OF THE U.N.-AFFILIATED INTERNRTIONAL -
, ATMit ENER6Y AGBICY: MNS 3LIXs FLEN OYER THE REACTOR THURSBAY AH '
- Sall M SHIET TELEYISION 'THAT SNOKE WAS COMINE FROM IT. .
'1 NT'ROSEE $$13 TODAYS J'THE FIRE IS OUT." .
, NE'SRIE THE SM0KE SEEN THURSMY NAS LIGHT GRAY AU APPEARED TO COME. '
.FR$51 NGL 3ERING Saps LER3s.30R0s ANB 30LOMITE THRONN OVER THE REACTOR'
, T8 SMTHER TE FIRE. HE SAI) SM0KE NAS THICKER AND 3ARKER NHEN THE FIRE-
' Ms Mu1Ns. .
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.. cv Re: F01A-86-335 APPENDIX I RECORDS MAINTAINED IN THE PDR UNDER THE AB0VE REQUEST NUMBER
- 1. 5/6/86 Telegram to multiple addresses from NRC - IP
Subject:
m Information on Effects of Soviet Accident (3 pages).
- 2. 5/8/86 Memorandum for Smith from Speis,
Subject:
Attached Offer of U.S. Aid (3 pages).
- 3. 5/8/86 Status Briefing on the Chernobyl Nuclear Accident Presented to the Advisory Comittee on Reactor Safeguards (49 pages).
- 4. 5/9/86- List of published NUREGS, Articles. Testimony, Statement, and list - Sumary of Environmental Results from NRC Licensees, May 9, 1986 (2 pages).
- 5. 5/12/86 Sumary of Environmental Results from NRC Licensees (2 pages).
-6. 5/12/86 Memorandum for Distribution from Speis,
Subject:
Daily Status Report - May 12, 1986 (2 pages).
- 7. 5/13/86 Status Briefing on the Chernobyl Nuclear Accident -
Presentation to the Comission (21 pages).
%' 8. 5/13/86 Sumary of Environmental Results from NRC Licensees w/ cover page (3 pages).
- This record is filed in PDR folder F01A-86-517,. Appendix B #3 4 . 4. *We, yl Aw-w.%'!dpks a.. as;
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