ML19347A385

Chapter 4 to State Univ of Ny at Buffalo Final Hazards Summary Rept,Revision 2, Reactor Description

ML19347A385
Person / Time
Site:	University of Buffalo
Issue date:	09/23/1963
From:	NEW YORK, STATE UNIV. OF, BUFFALO, NY
To:
References
NUDOCS 8104080569
Download: ML19347A385 (31)

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{{#Wiki_filter:. ), and a high level clarm. tkxiuun sensitivity of this esseubly is 2.4.x 10'O uc/a1 for the.0.02 How bot..s of R:103, and the clarm point I'" is set for this concentrction. In order to check the intearity of the filters, and also to have a record of the gross beta particulates released to the atmosphere, a particulate sampler draws air fr om the exhaust side of the filter bank throu3h a piece of filter paper. The filter paper r is chenged at a regular interval, and is counted for gross beta activity follouing the decay of radon disintegration products. = IV. REN DESCRIP1'ICU = A. General i The Uestern Neu York Nuclear nasearch Center reactor is a hatro- { geneous system of normal water and solid fuel. The core is iunersed t= in a tank of water, which is surrounded by a shield of high density g and normal concrete. Control of the reactor is accomplished by the incertion or removal from the core of neutron absorbing rods. These j" control rods, as well as the various neutron detecting chambers used l- { for instrumentation, are suspended from the bridge which specs the t= reactor tank. The reactor is operated from a console located in a room near by the bridge superstructure. l .i Hajor auxiliary equipment includos a priuary cooling system consisting of a pump, hold tank (for redio nitrogen decay), and a heat e6 er; a secondary cooling systen which circulates water from i' { 3 s- [ the tube side of the heat enshanger to a coolia6 tower; an emergency spray system for cooling the core in the event of 'groes water loes; 1 L 1- + C 810 4 0 80 d(a [ V["..

and a radiation monitor systeu. One decineralizar system purifies all makeup ~ unter for the reactor tenk, while another system continuously purifies a side streau of reactor water. Fixed experiraental facilities essocicted with the reactor [ include a hot call with a pass-through tu's and ganana irradiation capability, two pneumatic conveyors, six six-inch round beam tubes, one cwelve-inch squere beam tube, and a 3raphite thermal column. Reactor Characteristics l Type Tank (or swinaning pool) i E Core Heterogeneous 67, enriched U-235 ] as UO, sircaloy-2, normal water 2 Initial critical Mass 13.31 kg. U-235 Power Two megawatts 2 Average Thermal Flux 3.32 x 10 n/cm 7,,,, am, Moderator Normal E 0 2 Reflector Norac1 Ego Coolant Normal E 0 2 Shield Nor.nal B 0, lead, normal and high F-*= densityfilmenite) concrete. Er/H O ratio 0.385 2 3. Reacter Tank } i _3 The reactor coro ic loc ted acer the bottosa of a veter-filled, aluminum lined, re-enforced concrete tank. The tank fa roughly hexagonal in cross section, with a width of 14 feet at the top. Approximately 15 feet from the tank top the tank interior is stepped to a width of 8 foret to=== M aca the increased thickness , of well shielding required in the immediate vicinity of the active fuel. The ilmenite somerate well is 6 feet thiek in the louer section, -I -+ 2

l' im wheress only 1-1/2 feet of concreto ic required in the upper section. ' _ = The aluminum liner is 1/4 inch thick, cad a seelant is used to pravent ..-.....--..-- ---... - ~ -. -- [ Ug corrosion of the liner due to contact with the concrete walls. 1 The liner is penetrated as follows: (1) si::, six-inch round, and one, twelve-inch square, )E ba*= tube Ports radiate from the core around the lower 3 tank section. t== t-E (2) One penumatic conveyor system enters near the top of ]1.,, of the upper tank cad terminates at the upper edge ~ g of the core. 7 (3) Directly below the core and plenum is the coolant {,, discharge line to the primary pump via the hold tank. I (4) Pour coolant return openings are located several inches above the floor of the tank. ~

== (5) A drain line is loccted in the floor of the tank, roughly under the square been tube. = i ~ (6) A pass-through canal provides a passage between c*s upper portion of the tank and the het cell. (7) Eight emergency coolant nossles are loested in the Iower taak section, just below the step. l l w. (C) Five intakes for the domineraliser system are located IE just below the top of the tank, on the air leek side. I. E (9) on the tank well opposite the airlock are located i the four domineraliser rsturas. 1 ( l

.[,

storage cylinders for fuel elements are arranged around the I upper section of the lower tank en cil fases easept the boek wall =, (oppeette thermal solumn). In addition, a reek for eight used L~ s seans irradiation fcoility. elements is 1eented on the task wall esames to the het es11 to provide t ) C. Core aqd.Sunport 8ttuature o= The fuel is inserted in a grid plate, utdek is a slab of a1d==, 3 I p=. bered La a 6 x 6 array of holes. The grid and fuel are asusted es, j- .W. b' L + l Tx L

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1 i nd supported by, the plenua chamber, uhich chennels the coolent flotr eacrging from the fuel elements to the discht.rge pipe located in the center of the tank floor, This pipe servec as a support for the entire a am plenuu and core structure. Aluminum super-structure above the core is provided to suspend a lecd thermal (heat) shield on the core side opposite the thermal (neutron) column and to provide a guide rack for o w., .s~ neutron detection ion chambers. k D. Fuel i The reactor core is made up of eighteen er more fuel assemblies. Each assembly contains twenty-five fuel bearing, pins. Each pin is a hollow tube consisting of a 0.020 inch zircaloy-2 wall filled with sintered UO2 pellets. This thichness of zircaloy-2 is adequate to

b' contain all fission fragments under normal circumstances. The uranium is enriched to 67. in the 235 isotope. The UO Pellets necsure about 2

l~ 0.42 inches in diameter and u.60 inches in length. The finished pin is 0.47 inches in diameter and 26 inches long. Approxinately 30.2 I, grcms of U-235 is contained in each pin. The fuel pins are frctened mechanically into groups of twenty-five with aluminum end fittings = and era then plcced in an zirenloy box; the finished assembly has a ~ lI cross-section measuring about 2.7 inches by 3.2 inches. At the lower cnd a guide tube (or nose piece) is cttached, bringing the overal'. length of the assembly to about 30 inches. This noscpiece is inserted into a hole in the grid plate which supports the entire fuel array. A small pin set in the grid plete mates with a 1. ole in the nocepiece

lI shoulder to position the assembly axially. A dowel is inserted between side plates at the top of the assembly and serves as a handle for 7 f 1

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~ i moving the essembly. Both ends of the assembly are open so that cooling water may flow up or down t.round the fuel pins. 'E E. Cooling and Purification 'g The primary coolant, which is drawn down throech the fuel ass-A licis to remove the heet of fission, is collected in the plenum which supports the core, and flows to a hold tank buried under ground. A hinged, counterbalanced safety flapper valve is located on the side a of fhe plenum. t f"' When held closed by pump suction in the plenum ~ (operation over 100 DI), all coolent water must flow down through the fuel. If, however, a power of 100 I5i will not be exceeded, the primary pump need not be operated, cod the flapper valve will remain open to allow cooling of the fuel by upwsrd convection of water. The primary 3 water is conducted from the plenum to a hold-up tank of 5,000 gallon g capacity, buried outside the containment near the building entrance. Here the short lived radionitrogen (7 second half-life), formed by activation of oxygen passing through the core, decays to tolerable levels. From the hold tank the coolant passes through the primary pump at 1200 spe, thence it flous to the shall side of a heat exchanger, i where the heet is removed by the secondary water flowing through the i heat exchanger tubes. From the heat exchanger, the primary water raturns to the tank through the return parts, located,just off the tank floor. The secondary water loep consists of a pump, which delivers 800 l l gym, the tube side of the aforementioned heat exchanger, and a single fan coolica tower loaned at the rnar of the building. t t - ^ ~ ~ ~ ~ ~ - - - - ^ - - ~ - - - ~ - - ^ - ^ ^

FIGURE 5 SOLENDID VAIVE PRIMARY, SECONDIJtY. AND DEMINERALIZER SYSTE!IS - M 'Ol-fXt--- - CITY WATER REACTOR N TANK Y % TEMP BULB 4L COOLING g HEAT EXCHAIXIER A / ORIFICE,% j s TWER i

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TB E F TB gg t' VN3 -v .x^ V N.' r.T\\800CPH .N -- SUHP e 'g '/ PUMP CITY WATER PUNP '( {@p 7f,C. );' 1200 GPH ) .N '~ HOLD S-.. TANK C' FILTER 1 c.' 'n' 5 d - M- *

• C 1-STORACE j

> TO BEAM 'IUBES TANK / +. .a ~-l 1 m l FIDU l CUNO

DEH, C/

HETER-DEM FILTER \\l h ADAMS

r. '*

$7 1 7 FILTER CM i f T ds j i l Ml / ? l% e v.i og j.,_ m vs , s.., .f y __.-s,. \\ p@p .h 'XI N CONDUCTIVITY PUMP ./ IETER v - -=

Characteristic Temperatures 0 Tank temperature 100.0 F 'g Primary Coolant Hect Exchtnger inlet 111.3* F

=

0 Ecat Exchanger outlet 100.0 F Secondary 0 Heat Exchanger inlet 75.5 7 . Heat Exchanger outlet 92.50 F ~ Auxiliary units include the mche-up domineralizer, which removes impurities from the city water prior to use in the primary system, and the ciecu-up deminerclizer, which treats a 20 gpm stream of primary water drawn from the top of the tenk (through screen.J intche ports). ~ Indicator lights are provided for all console mounced pump ~ switches. In addition, to ensure adequate cooling of the core in the event of gross loss of water, a manifold with eight 1-1/4 inch shower heads is located in the lower tank caccion jtst below the scep. This system is connected directly to the city w..ter mein and is actuated by a pressure detecting switch operated by the reactor tank water head. F. Shim Safety Rods and Drives The drive 9aism consists of a motor, a worm and two spur gear reductions, and a rack and pinion drive. The limits of the stroke cre set by adjustebic, esa-operetsd, snap action switches mounted on the rack guide cover place. The standard stroke for the rod drive is twenty-four inches. Drives can be so positioned as to cover any of ~ the spaces in the grid place. 1. Shim-Safety and Rezulatium-Sc!ety Hods: The four shim-safety rods, and the regulating-safety rod are comprised of flat absorber blades of silver-ic. tium-cadmium alloy about J_ 1. .,. - _. _.. - ~. 4

I O.10 inches chick by 5 inches vide by 24 inches long. Each blode is cttcched to a sheft which extends chove the watcr curface, where it is capped with c usanctic sect. An out-of-weter magnet in contact with th.c seat supports tha rod cad extension. In ad Mtion, e hollow shroud chout 0.43 inches thick, 6 inches vide and over 4 ft. high providas e guide inside which the absorber blade travels. Ecch shroud is restrained verticc11y by a t.ube which is concentric with the er. tension shaft, cud which is positively atteched to the mounting picto for the rod drives. This tube also serves es the s1 cove for the shoch absorber asser bly which is integral with the sheft extension just below the surfcce af the pool water. The shiu-sefety rods, are worth ebout 67...h/h each, on the average, with the regulating-safety rod positioned in che core so cc to limit its worth to about 37. /. h/k. The four shim-safety rods, cad the regulating-safety rod ~ cre cctuated e nnelly; either individually, in pairs, in groups of three or four, or as a gens of five. The regulating-safety rod ocy clso be positioned autocatically in response to a power demsad setting of the servo control. A console mounted light actuates when each drive is coupled to the geng switch. p Rod contact indication is derived from a microswitch at the scanet, and is displayed on the reactor console. Position indication ~ in n.w.ated by a parenticuaror driven throigh a pair of beval y,oara l. on the rech pinion shaft, and is dispicyed at the console either on l. individual gauges, or on a digital ratiometer capable of readout to ? hundredths-of-an-inch. 2ach speed can be varied by use of a selection of spur gear . t1 4 ,,r- .F., m y.

I reductions. Design speed is 8 in/ min for the shim-safety and regulating-safety rods. 2 Transient Rod: The transient rod is similarly driven by a rack and pinion drive; however, it is not magnetically coupled to its drive.

Incecad,

= the above-water portion of the shaft extension of the rod is fitted with a piston, which moves under pheumatic pressure in a cylinder. A belanced pressure system is utilized to drive the rod in either direction. A shoulder on the drive unit supports the transient rod shaft extension by engagement with a collar attached to the shaft. = A schematic drawing of the syctea is given in Figure 16 A system of limit switches an air supply, and appropriate valves effects the initial ion of the pulse. A description of the sequence of events constitutire, a transient follows in Section J. E Ec transient rod is identical to the control rods in dimensions and coc: position; however, it is so located in the core as to minimize its worth. Moreover, the available worth will be L mechanically limited to the value associated with a 90 megawatt-

s. _ d p.1s..

j G. Instramentation ~= 1. Steady State Operation: I-l Noutron detectors for reactor control include four ion l l, chambers, and onc uranium-235 lined, fission chamber. Of the four l ion chambers, suspended from the bridge, and retained by a rack on (= the cora superstructure, two are uncompensated for gasmia activity l and feed the safety amplifier, while the remaining two can be coupon- = sated for i M L I

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l c N VALVE %y, " EXHAUST LSI }I PRI -PRESSURE AVEL REGULATORS }. SWITCHES PULSE POSITION DRIVE INDICATOR -CYLINDER PRESSURE PULSE ROD GAGES POSITIONING DRIVE I LS2 PRESSURE P SWITCH g PR2 LS3 V2 ACCUMULATOR EXHAUST LIMIT SWITCHES FLOW ,I CONTROL MLVE r1 LS ( MATING COLLAR l LS5 I ( SanCx MEC!iANICAL A880R8ER STOP T -l. 1 [ CORE PULSE--+- - ROD I_ PULSE ROD MECHANISM g n -is n - - -,. -, - _,,,, -.,., _. ~.. _,., _ _ _, - - -,. _ _. _, ~

scuna f1te:, cnd food the lineer and log-N power chcnnels. Figurc XV I depicts the five basic instmcat chennels which provide information for c.fo control of the recctor. (c). Ccunt-rate or Start-up Channel The detector for this channel is an urcuium-235 lined j f fission chcuber opercted vertically by a standard Alf rach and pinion 5,. I drive occhanism. The fission' chsaber signal is fed to a pre-emp, thence 1 amplified further by the A-1 cglifier, uhich drives a strip I chert recorder through a count-rate meter. The A-1 cmplifier clso drives u sceler which can be used to take pre-determined counts during i f critical e::pericants. This channel is the most sensitive of all 5, a l neutron detectors, and therefore is used for initial start-up. (b). Lineer N Power The second most cancitive channel is the linear N power. t,* Its signal derives from en electricc11y compensated ion chcaber mounted in a rack to the rear of the core. The chsaber can be positioned vertically to adjust for changas in flux geometry, and the compensation feature eliminates the false power sig[1 caused by high level samma l radiation. ' The current from the ion chember is measured by a uiero-micro amanter which furnishes a signal to a strip chart recorder. i Since respono's is linear, sufficient rsage selection is provided to -1 I permit measurcuent of reactor pouer in the range of one watt to two nillion watts. I (c). Lon-N Pouer Channel i The second compc.4ated ion cha:aber feeds the log-N and ' { period amplifier. In the applifier, the tog chsaber current is passed i l M l -j I, I I

through a therrionic diode. The voltage across the diode is proportional to the logarithm of the current flowing through it. The voltage out-g 5, put from the diode is amplified and the stepped-up voltc;c is impressed on a voituoter (log-N power actor), and on the log-N pouet recorder. To obtain period mecsurement, the output of the logarithmic ccpli":ler

== is fed into en RC differentiating circuit, which results in c current that is inveracly proportional to recctor period. As e::pleined below, thic chennel furnishes the signal to the safety amplifier for period screu. (d). Sciety Chennels Tuo uncompcassted ion chcabers feed current to the scfety cuplifier. This unit provides controlled current for the electroccanets which hold the scfety rods out of the coro, as vell es volcace for the ion chsubers. Control is accomplished in the follouing Qannor; Sach chcaber provides et sigasi to the grid of duc.1 triode vacuum tube uhich operates tuo sensitive high opeed plate I current relays. In the event that one, or both chcabers detect en abnormally high level of reactor power, any one of these four relays u can cauco cudden cutoff of the cagnet currents flowing through four = vacuum tubes by direct control of the grida. Since this action can be I completed in about five milliseconds, it ic cellod a " fast" scraa. As pocitive backup for this system a second set of relays simultaneously l.. turns off the magnet power supply. Decay of voltage from this supply tches slightly longer -- about tucacy milliseconds -- and is, therefore, ~- celled a " slow" scrcu. The slav screa is also used for scrcms .w iE

t El originating outside the sr.fety mplifier (see Table 'C;III). g,! In cddition to the cerca et hi;;h power level, e period screa cepchility ic provided throuch the log-N cud period emplifier, which connects through c cet of contacts to the sciety emplifier circuit in the saue acnnce that the Zau-fest sc cu relay contacts ti cro connected, pc::1od scrca ic, therefore, e fest scram. Othar l contretc are provided from the Lo3-H cmplifie.r to cut off cagnet pouer supply. A rod reversal ic cctucted at 1107. reactor pouer by of a Larson acter relay cocaccted in ceries uith the No. I meca safety pouer level acter. This ceter relay is located inside the console. (e). Te:nperatures Temperatures in the cooling system are measured and are presented on a six-point n:eter ao follows: = Reactor tank (core inlet) ,i Core outlet ] Heat exchanger inlet (primary) Heat exchanger outlet (primary) J l' Heat exchanger inlet (secondary) l } Ecac exchanger outlet (secondary) In addition, the core differential temperature is n . red a.ons. u t.d.,.r. I 0lg l* J J l I>; '1 n,,,,.

5 3 ~ 2. Trcnsient Operation: } For trant4. ant operation of the reactor under the conditions described in Par', A of this section, the dotermination of the initial esyntotic period of the exponentially rising pover, the exact value of the peak power, the shape of the pulse in the region of the peak, and the integrated energy release are of primary interest. The power burst measuring instrumentation'aust therefore record or display, accurately, the power pulse from a 1cvel three to four decades below the peak power, up to the peak power, with exact determination of the peak power. Information on the initial shape of the power burst pulse is desirable. The reactor power burst will be measured with two ganana compensated, high level neutron burst fission ebsmbers. These chambers will be housed in waterproof containcra located adjacent to the core. The dynamic range of flux during a power burst to which each chamber 10 17 will be exposed is approximately 10 to 10 ny, for the peak power of 10,000 megawatts. In' formation from these detectors will be processed and displayed generally as follows: The signal from chamber A (Figure 18) is applied to a low noise, high Sain linear operational amplifier ~l which feeds its signal to a fast, high level, solid -3 state, logarithmic voltacc converter with a dynamic rango of three decados. 'the output of the linear -g operational amplifier. *.11 be dispinyed on the screen ot ) an oscilloscope by acano of a time based triggering method. The oscilloscope trace may be photographed during each pulse in order to provide permanent information. ~ The output signal from chamber 3 will be appued to a lov icvol linear ecpliliar, the output of which _a applied simultanoously to a power. peak following e - -

t i I.'l l i y;cg;-. 1711 INSTRUMENTATION BLOCK DIAGilAM i 1 1 //sf Yo / j Lcrson UIC i yeger i \\' + Slou Scfety i Scrams haplifier l'.1 Sciety. lod Drive Coatrol I g,.; l % nuel 5 *- UIC l Or. ts Inhibits (4-) neverses h E i I'*- L3N& CIC Period g,3 g Drive y}af,' ors P.eCOrdCr kap. yt e_. ) I,] I I-Pouer htcrr.al Position Supplics 20'2100 3,, Indicators De v n (2) Mater decci .A n / 1 Micro-Hicro Linear '3

• E' CIC A:neter D

c accorder l uc w a i Log Los l'; F.C. Pro Linasr Count Rate Count Rete A.?. Acplifier 15eter 2ccorder l i

• r

-.I 4 1,, Secler 0 7 t .4 SC -n-- -a-r, - - - -.. ~

I IM IW i i I I I I ~ l I I I I I I IE I t" FIC XVII PULSE INSTRLMENTATION BIDCK DIAGRAM i / ~ Transient Signal Condition A 4 I Detector #1 -~~ ing Unit #1 ~ ~ ~ ~ l j. (Last 31/2 Decades) M.V. Power Supp17 4 Adapter Unit #1 1 / Ion Chambor Nigh /. H.V. Power Supply Power g,,1\\ j Burst Channel . M.V.. Power Supply -{- ~ s, fAdapter Unit #2 Weutron Flus b ~~ ~ Transient Signal Condition Pulse. ^ ~ ~ ~ ~' Mon (toring{ ing Unit #2 ~ , Detector # 2 g (t... i f Last 3.,_-4 DecadeO g j-Lowg.I Linear N C g lSignalCondition g js., ... Detector.. ing Unit #3 (First 31/2 Decades) ~ ~ ~ - I D N.V. Power Sepply Adapter Unit * ? Ion Chember

• 2 N.V. Power Supply

.= t H.V. Power Supp1M Adspter Unit

• I"-------

-.i To Log N Detec to r

• T -- ---~~

1 i 4.* h a

r' M d T 75=d ~-~ M ~ SED A--n 2SEE &~ M M o.- /) 8 ,a J /L / ,L J .L.J e d + d im W f im I I IF E M Im im Im W Im W) W W FIG XVII 4 PULSE INSTRtRENTATION.RIDCK DIACRAM (CONT.) Logarithmic I __A Linear DC i Amplifier #1 Voltage Conver- - - - - - - ~ " Digital Power ,go,. Unit ( ~ ) Indicator Manual Reset [. lI !~ l Pceer Peak l lFo11owingUnit ( ) Digital Pewer loPedance t, 3 Me JREEL.jor' ' Matching Unit ..t!.2c!S E p I I R e.w.r e Linear DC

+

ate tin 6 l Amplifier f2 y, 4 i ._L Linear DC Logarithoie 3 Dual Trece Amplifier #3 Voltage Conver-t- _y Ampiggr sg i mann e 8 D Linear Micro-To Linear N Power Pulso V .s ' Nicroaaoeter

• Recorder
• Sinulato r

~ l -.~ I l a dethode Ray I I s oscilloscope t l 1 i 2 =.

'S unit and a pouer inte,Teatir.g unit. The peak following J unit will consist basically of a diode connected so that a condcasor may be charged but not readily dis- ,g charged providing an output voltage of the unit "g representing the peah value of the input pulse. & power integration unit will consist basically of an operational amplifier with capacitance feedback and resistive input, providing the time integral value of um the input voltege pulse. The output voltages on both units can be displayed digitally on a digital power indicator by selective control, providing a digital readout of the magnitude of the maximum amplitude and the total integrated power of the power pulse. The low icvel channel will make use of the existing linear N compensated ionisation chamber. The signal of this chamber will be fed to a linear DC ampliller which output is applied to a logarithmic voltage TE conversion unit with dynamic range of 60 - 80 db. The 15, output of this unit is displayed on the screen of a cathode ray oscilloscope. b oscilloscope traces can be photographed by means of an oscilloscope camera if desired. A water temperature transducer will be located above the ,il reactor core to initiate a reactor scram if the tauperature exceeds 200* F. 3. Radiation Ibnitors: Levels of radiation in work areas are monitored continually, h areas so protected are as follows: Neutros deck (three stations) naactor bridge IWC call b streams of air and unter which are monitored, are as Lg follous (covered in detail ta Section III): ) .m y-neactor coolant (or abnormal insroases) f_ Con M - auhause ~41-a f

i Exhaust from hot call, experimental facilities, and hot chemistry laboratory (particulate and gas) Waste hold tank discharge 4. Miscellaneous: Over and above the annunciation situations listed on pages 63 and 64, indicator lights on the console depict the condition of the hydraulic systema for both containment damper systems, as well as the positions of the dampers. Similarly, lights indicate the condition of air supply to both sets of air L, lock doors, and to the truck door. l Auxiliary scram buttons are located at I%, the bridge, and on the neutron deck at each beam tube side of the shield. -L L 1' \\- l k_ r DL L i 8

• 62=

TABLE XXIII Scrams, Reverses, Inhibits, & Annunciations UNIT ACTION 6 AENUN-CONDITIONS DETECTOR INITIATUE ACTION CIATION >120% Full Power Uncompensated Ion Safety Amplifier Fast Scram

1

" Safety Amp" 4 Second Period Compensated Ion Img-N & Period Fast Scram Chamber Amplifier " Safety Amp" ~ Safety Amplifier 1 Manual Scram Ceram Button 2elay Slow Scram _E " Manual"

• Flapper open Microswitch/ Zag N
• Mlay Slow Scram

'1, (Above 100 XW) Recorder " Flapper"

• Low Flow Pressure Transducer

.Zalcy Slow Scram 1 " Flow"

. 3

• Water Level Float Switch 2.eley Slow Scram

" Water Level" open Circut to Relay in Safety .'cicy Slow Scram Uncompensated Ioni Amplifier " Safety Amp" CLember 1 Temp *. Above Core Tempe ature Eulb

slay Slow Scram r

>200 F > Failure Relay in Safety T.alcy- " Safety Amp" Slow Scram Amplifier (~ >110% Full Power Uncompensated Ios Larson Meter Reverse Chamber "High N Reverse" l- <15 Second Period C-7--ted Ion leg-N & Period Roverse Chamber Amplifier " Period Reverse" Rhgu'lati hc EiO_O W zg g.,. g e,

• po.g l

l' Ing-N Selector log-N Amplifier Belay Inhibit of i-E Switch Not on Switch Rod LE " Operate" Withdrawl l* " Log N Inhibit" Iag Count Rate Suitebes

eley. -

Inhibit of F <2 CPS, >9800 CPS, Rod or shart Drives /Iag= Withdrew 1 N < 4 watt " Start up L-, Inhibit", H ..,-<--.,-,-,,-..,--,,-,,,.n., ,,.,--.,,.,-,_-,.---..._.._.,-n,,_,- ,._,,,...,,,_m.,,,-,. -n, -,--n-,

I TABLE XXIII Scrams, Reverses, Inhibits & Annunciations (cont.) ,i UNIT ACTION & ANNUN-ColfDITION DETECIOR INITIATI.NC, ACTICU CIATION a High Excess K Microswitehes

talay Annunciation g

"High Excess K" Domineraliser Inlet Bimetallic Strip Relay Annunciation Temperature >109"F "Demin. Temp." Core Outlet Bimatallic Strip Relay Annunchtion Temperature > F " Core Tamp." { High Conductivity Resistance Bridge Relay Annumistion Desineralized E O i "Cond" Abcornal R Level.F1 at Switches Relay Annunciation 2 I_ Auto Failure " Water Level" Servo Deviation Rolay Relay Annuncistion (. " Auto Failuro" Emergency Valve Microswitch Relay Annunciation Open "Emerg. Valve" Manual valve open Microswitches Relay Annunciation " Manual Valve" Regulating Bod Microswitches Relay Annunciation < 201 > 701 " Thinning Ee- / quired" l, Power > 100 Kw Three Position Mode Relay Slow Scram Switch, I43=N Amp 11.. - fier Switch i l 1_ ll~ I , l CIndicates scrans which ces be bypassed with a key. m_ l !_ -n. -,.~._e..,.--. ,,,,n- ,--,v ,, -. -, -.., -., +, - -. - - - -. - -,, -. - - - -. - - - - -,, - -, -, -. - -. -, -.,,..... - - -,. - - -,.... - -.

H. D:perimental Fecilities 1 Core D:perinents : ] 2, In e typicci loed!.nc, one or core irrediation speces 18.11 be 5 provided in the cctive core, to ta':e cdvcatece of the high flux of the core rccion. Tocci trorth of c::periments to be pinced in core locations vill not c::cecd 2.0% 4.h/h. Tha worth of each e::periment trill not execed 1.5% / h/h. Irradiction ecpsules ucy be either open 13 to tenk veter, or voided. Scroal neutron fluxes up to 3.4 x 10 n/cu' /sec. vill be cvcilcble in core locations. 2 Boem Tubes: Six 6-inch becm tubes are provided to pass neutrons through the biological shield. n o neutron becuo will be used for neutron ,,g E 7_ diffraction studies, neutron spectroscopy, and time of flight ueasure-ments. The basic tube asseubly consists of en cubedded aluminum j sleeve, a retractable aluuinuu liner, cad c set of interior shielding plugs of canned borated barytes concrete, and of leed. The beam tubes can also be used as dry irrediation chcobers for small sas:ples in radiction effects studies. Thus, saaples can be placed et the face of the core and casily monitored without the waterproofing precautions 3 13 necessary if placed in the pocl. Fluxos up to about 1 x 10 n/cm /sec. are available et the core ends of these been tubes. A 12-inch square chamber is provided for the dty irecdiation 2 of large samples. Again, a flu = of cbout 1 x 10 n/cm 7,,,, 3,,y,gt, able at the core end of this been tube. 3. Rabbit Tubes: Two 2-inch rabbit tapes are provided for the rapid trans-port of samples to and from the face of the reactor core. These tubes i. 65-

i will be utilized fo.: the production od chort-lite.d isotopes to cupport i the cedical, pharaccologicci, and physicci progreac. They tilli clso be used to provido short tern, coatrolled irrediations to cueil samples. 4. Therx 1 Column: The graphite thermal column provides a source of relatively pure thermal neutrons. Imedictely adjacent to the reactor core is a 6-inch thich lead shield to bloch gemac radiction. Between this shield end the tack wall is en aluminum clad graphite nosepiece 2.5 feet thich. Beyond the tank wall, in piccc of the usual high density concrete shield, is a cavity 4' x 4' x 6-1/2' stacked with graphite stringers. The working chamber is 4' x 4' x 1-1/2' deep, but een be expanded to 6' x 6' x 5-1/2' by withdrawing the movable shielding plug four feet and adding some peripheral portable shielding. = i' 5.'Gemme Facility: ?. By utilizing spent fuel elements, and a 2' x 2' cevity l 'in the concretc shield between the hot cell cad the tank, g.w s irradiations can be accoammodeced. A 2 3/4 inch thick lead shield can be lowered by a winch into this cavity for shielding purposes. A total of eight irradiated elements in a row can be placed et this facility. j, 6 Medical Facility: The concrete shielding c ' the east well of the tank is o removchle, to permit the addition of a neutron therapy facility in the future. p l e., 66-i* W .~., .~ - -. ~ - -

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L 7. Hot Cell: The hot cell is adjccept ts the west well of the ersk end is connected to the t'enk by a veter-tight pass through lock for semple transfer. By suitchie arrangement of velves, the pass through lock may be decined of the water introduced with the scuple from the tenk, permitting opering of the lock from the hot call and removal of the sample by the remote manipulctors. Halls of high density concrete and e lead gicas viewing vindow are both three feet thick. Access 1 is either by c four foot by seven foot stepped door.or by a three foot stepped plug in the roof. A one-ton traveling crane, remotely e oporcted, services this facility. The hot cell espacity is 25 kilocuries of cobelt-60. 8. Fission Pinte: Ucenium aluminum alloy s:m: M.ning approximately 1 kg. U-235, cicd with 0.025 inch cluminum comprisos the 13" x 13" x 0.5" ~ fission place. The plate will be used in the thermal colu n cad 12" beam tube to provide a fission neutron spectrum. Minimum approach to core is 5-1/4 feet; hence 'there wi.11 be no measurable intesaction. Maxis 4 curie content within reesonable acessa time is calculated to be less than 10 curies. I. Exr.ariuental Pro.trem it is impractical to provide a comprehensive list of all materials which may be irradiated by the reactor as part of the research prograu. l In lieu thereof, the following is a list of the types of materials ~ which may be irradiated, but it should not be sonstrued as restrictive for materials to be irradiated in the futures a._, i ,_ -..-~.-, -.-,

n 1 Isotope E:oduction 60 115 S Co Cd g,77 9 IO 64 124 Fo F g 3p } Na As P M2 42 92 86 90 g 3 7 $l Reactor Mr.terials Testing Refractory metels end alloys Organic moderctors Urcniu:a-235 compounds (milligram quantities) Urnulum-233 compounds Cross Sect'.on Determinetions i Eleaeats 3 to 83 $0ml Det.2cge Stud'.cs 0 g Electronic couponents 'g Plcstic materi:1s Ceramic acterials Sample Contciners I Quartz Behelite and other phenolics Lucite Staniless Steel Aluminum Polyethylene lI 1Esec11e.ncous l Lobster nerves, blood, other biological specimens l The following are wats.r'als whose irradiction would be prohibited: (1). Compounds or clouents which are excessively corrosive to the material of encapsulation.- (2). Any unescapsulated compounds or elements which i through their physical or chemical nature would cause a contamination hasard following irradiation. l1

i (3). Any ceaple uh.'.ch would cause a change in core reactivity > 1.57. t.h/h. (4). Any alcments, mi::turcs, or counounds which', in the I opinion of the operr. ting coe aittee, through the irradiation process, would cause foriction of ges within the c:psule to the e:: tent thet resulting pressure unuld ccuse the cepsule to burst, or otheruise endencer the integrity of encapsulation with resultant uncontrolled radiation hczard. E:ch servico must be approved separately on an Irradiction Request Form prior to the irredictioa. Irrediations which cre routine and not unusual and premt no safety prob 1cus will be cpproved on this for;n by the Director, the Operctions Manager, and the Hes1th l Physicist. All irradiationc which cre unusual or non-roucine will be subed.tted to a meeting of the Huclear Hazards Coerdtte for advice and recor:rende. 1.pndling procedurcs. J. necctor opm ation = 1. Initici Startup and Aporonch to Criticality: Prior to the initial loadin3 and start-up, all control circuits and interlocks are coupletely checked out. A complete chech-out of mechanical equipment, irradiation fecilities, cooling and purification system is performed. Pulse height settings for both operating and spara fission chennels era determined. For Luitial loadinsa, all ion chani:rs are ',owered as fer es possible; the design permits lowerits o epprossinately the top of the recctor core. This risults in more sensitive safety amplifier calibention and correspondingly lower power level trip. The linear-N ehanaal will give indication during initial loading to criticality. The loading is performed very slowly and according to a well established and practiced procedure. The leader is in constant l ~ l I- ~..,. -. ~ -.s - - - - -,...... - - -. - - ~

communication with the op.erator by means of the containment inter-I communication system. Loadings are made with all rods at shim range and counts are taken for reciprocal count curves with rods fully ~ ( vithdraun, and with rods at shim range. Thus, a check on the prediction of the critical mass is available after the loading of each element and before the loading of the next. i Criticality or slight supercriticality is indiisted by a straight line or increasing trace on the linear-N recorder and the i log count rate recorder, when the source is removed from the core. 2 Normal Operation Start-Up: (a). Steady State Operation Prior to reactor operation, safety and control systems are checked out. The regulating rod is then withdrawn to its mid-point. The shim rods are withdrawn manually to bring the reactor to a stable, positive period and the reactor power is permitted to riso to the desired level. Power IcVel changes will be made on approxi-mately thirty second periods. The " Range Selector Switch" is changed or stepped, as required, to keep.the linear level recorder on scale during power 1rJa1 changes. As the desired power level is approached, the period is increased. Uhen the indicated power reaches one (1) per cent above l_ the demand set point, the period is increased to infinity then the reactor is placed on servo control. Thus the initisi correcting revement a of the regulating rod will be inward. Low power operation (below 100 IN) required only upward natural convection of pool water through the sore for cooling; that is, the flapper valve will remain open. j L

I i Iligh power operation requires forced coolant circulation, for which provision is made on the standard checkout procedure. The

== -flapper valve is closed, and both primary and secondary cooling systems are put in operation. I Final calibration of both power channels, and of the i i. safety channels, is performed against flow and differential temperature } derived pouer. = i (b). Pulse Operation (Typical) Preliminary to pulsing the reactor, the power 1cvel must bc Icss than 100 131, and the primary flow is stopped. The operator turns the three position reactor mode switch from the " steady state" to the " transfer" position. The reactor will scram if the power Icvel exceeds 100 IGI ut.en the "cransfer" position is selected. Next, the reactor mode switch is turned to " pulse", where-upon the primary purap and automatic control systems are interlocked out, and power is supplied to the transient switch. Next, the transient rod is inserted from its out-limit position the desired amount based upon the calibration curve. The reactor, which is nou suberitical, is again made critical by further withdraual of the shim rods. (The change in reactivity represented i by the movement of the shim rods serves as a check of the pulse rod calibration). The p,ver level is now increased to a value betwoon 1 ~ ~ and 100101, and maintained level. The transient switch is moved from "off" to " transient", thereby, initiating a pulse. ~ 72-

I i The transient rod is driven from tha core by.a pneumatic piston system, which utilizes a bc; c.ced peessure system. l Initially a valve, at the top of the. cylinder: ops.c< tor. exhaust, per-mitting the picton to drive upward. Toward the ano of its traverse = a shock absorber rapidly arrests the rod. At the end of its travel a collar on the above-water porcion of the rod shaft extension engages a lie't switch, which in turn closes the exhaust valve to repressurize the top of the cylinder. Simultaneously, the bottom of the cylinder is opened to regulated exhaust, and the transient rod returns to the i core. As it seats, another limit switch actuates valves to resume the balanced pressure in the cflinder. In addition, a limit switch l I i activates a signal on the console indicating that the transient rod has returned to its original position. In order to avoid a scram initiated by the c?sady ~ t

f. tate power and period safety channels, the transient switch is held in the " transient" rosition until the power level has returned to i

below 100 Rw. I After rewhing a power of less than 100 Kw. the transiwne switch is released, and the reactor power is stabilised to condition the reactor for the next transient. W m. . _ _. _,,, _.. _. _. _.. _,}}