ML20005G690
| ML20005G690 | |
| Person / Time | |
|---|---|
| Issue date: | 01/11/1990 |
| From: | Casey Smith NRC OFFICE OF GOVERNMENTAL & PUBLIC AFFAIRS (GPA) |
| To: | Thorne C STATE, DEPT. OF, BUREAU OF OCEANS & INTL. ENVIRONMENT |
| References | |
| NUDOCS 9001220172 | |
| Download: ML20005G690 (1) | |
Text
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Ig UNITED STATES
/
NUCLEAR REGULATORY COMMISSION i
m y
wAsmwovow n.c.rosss i
i
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VAN 21 12 Mr. Carlton E. Thorne. Director i
Office of Nuclear Export Control i
Bureau of Oceans and International t
Environmental and Scientific Affairs L
.U. S. Department of State i
Washington, D.C.
20520
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[
Dear Mr. Thorne:
Enclosed is an application for an export license (XSNM02495), recently received by the Nuclear Regulatory Commission, for the export of 25.226 kilograms of high enriched uranium for use as fuel in the BR-2 reactor in Belgium. The material will be converted and fabricated at CERCA in i
Romans France, r
Before taking action on this request, we would apareciate your views in accordancewithestablishedproceduresandfromtieoverallperspectIveof the Executive Branch, as to whether the proposed export meets the applicable criteria in the Atomic Energy Act of 1954 as amended by the Nuclear Non-1 proliferation Act of 1978.
Sincerely, l
I
?
C. N. (Mike) Smith, Assistant Director for International Security Exports and l
Materials Safety l
Ir. terr,ct ior.cl Programs l
Offica of Governmental and Public Affairs i
Enclosure:
Appl. dtd 1/4/90 (XSNM02495-France) cc w/
Enclosure:
i T. Hart, DOE R. DeLaBarre, 005 N. Martin, DOE M. Rosenthal, ACDA G. Brubaker, D0D G. Kuzqycz, DOC pyg12g y 900111 XS.NM-2495 PDC
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. - Do i
g TRANSNUCLEAM,INC.
E m0M4f-ll 004340 l
t January 5, 1990 i
, United States Nuclear i
Regulatory Commission i
One White Flint North F. ail Stop 3-H-5 Kashington,-DC 20555 i
Attn Mrs. Betty Wright Ret Export License Application l
TNY Reft NUK-504
./
Dear Betty:
Etclosed is an extort license application, the end use statemert and its reactcr checklist for your handling on the followings
(
23.574 Kgs Uranium-235, contained in 25.226 Kgs Uranium, in the form of metal, enriched to 93.45 w/o maximum Uranium-235.
The above figures include tolerences.
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Plear.e call me if you have any questiens.
Jery truly 'ours, t
..D f
Patricia B. Quain y
N Traffic Coordinator PBQ Enclosures
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1WO SKYLINE DRIVE
- HAWTHORNE, NEW YORK 10532 2120 TELEPHONE: 914 347 2345
- FAX: 914 347 2346
- TELEX: 6818082 MWMMN[ ] f-
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U.S. NC LE A~1 C EGULATOR Y COMMIS$10N Appnoyg3 gy g Aaj gSF$ilo APPLICATION FOR LICENSE TO EXPORT NUCLEAR sano22mRo3s2 MATERI AL AND EQUIPMENT (see trutructiorv on newsel
- jan ar -
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19 0 U 504 uSE j
- 3. APPLICANT'S NAME AND ADDRESS j Ri$
- 4. SUPPLIER'S NAME AND ADDRESS fits
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tcompete it entwo o not sept.er or meterwt tran=nuni.av. Tne.
U.S.D.O.E.
>. simE tt Acontss a.NAME Two skyline Drive e/o Martin Marietta Energy Systems, Inc.
i
- e. T E LE PHON E NUMsE M (Arse Code - humber - Esterven/
- t. CITY STATE ZIP CODE (914) 347-2345 Ext..3056 Cak Ridge TN 37830
- 6. FIR $T SHIPMENT
- 9. US. DEPARTMENT OF ENERGY 3CHEDULED SCHEDULED DELIVERY DATE EXPIRATION DATE CONTR ACT NO. IIIKnonn/
Three years from SeDtember 1990 N/A Saine as item 5 date of issuance To be determined
- 10. ULTIMATE CONSIGNEE l RIS
- 11. ULTIMATE END USE
'l' o NAuf tinctuoe piant or recarry names centre d' Etude de L'Enerofe Nucleaire Will be used as fuel for the BR-2 reactor
- m. sine E T auonEss in MOL, Belgium (see. attached end use Boeretano 200 B-2400 MOL statement and checklist)
- t. CIT Y - ST ATE - COUNTRY Belgium lie. EST. DATE oF FIRST USE
- 12. INTE RMEDI ATE CONSIGNE E l Rl8
. 13. 4NTERMEDIATE END USE l
e.NAME CERCA For conversion and fabrication of fuel e, sintE T Apontss elements Usine Des Berauds - BP 1114
- 4. CIT Y. s1 ATE - COUNTRY 26104 Romans, Sur Isere, France 13e EST. DATE oF FIRST USE
- 14. INTERMEDI ATE CONSIGNEE l 208
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- 16. INTERMED! ATE END USE l
e.NAME Tranenuciemire. s.A.
For transport purposes only im 6TREET ADDRESS 11 bis ruc Christophe Colomb
- c. CITY - ST ATE - COUNTRY 75008 Paris, France 1s. EST. DATE OF FIRST USE 16.
- 17. DESCRIPTION
- 18. MAX. ELEMENT 19. M AX, 20. MAX 21.
[o WElGHT WT. %
ISOTOPE WT.
UNIT SE nur ar co e r nj (U)
(U235)
Uranium in the form of metal, enriched to 93.45 w/o maximum 25.226 93.45 23.574 Kgs
- 22. COUNTRY OF ORIGIN.-
l
- 23. COUNTRY OF ORIGINr$NM l?*
- 24. COUNTRIES hHICH ATTACH l'
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SOURCE MATERIAL WHERE ENRICHED OR PRODUCED SAF E CU ARDS' Ist Known)
USA EURATOM
- 25. ADDITION AL INFORMATION (use separere sheer //neceswr/
At this time it is unknown whether there will b'e'any Austra'11an.or Canadian origin material, however, Transnuclear, Inc. will advise NRC is such is the case.
2s. The opplicant certifies that thes application 6s prepared 4 conformity with Tyt& Code of F ederal Regulateons, and that all information in this application es correct to the best of his/her knowledge.
3 %%{
- 27. AUTHORI2ED OFFICIAL
- a. SIGNATURE N
/
- b. TITLE Patricia B.
usin
-Traffic Coordinator 7
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L C.E.N./S.C.K. '
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Tat totessi es.7i. st.is.01 tra voie>st.co.gi VLu teses i
TLe o.nte. tem uei TVA 406.844.487 i
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J To whom it may concern I
1 suD ust :TArnaut The undersigned certify (=les) that the following mantaua quantities, i.e.
25.10 kg of uranhm 93.30 w/o U-235 enriched 23.42 kg of U-235 content I
in the form of U= metal furnished under the EURATOM /HKG-US/ DOE Uranium Enrichment Services Contract will be used as fuel in the SR-2 reactor at Centre d' Etude de l'Energie Nuc14 aire, Mol, Belgium.
OER06 Romanos hance shall perfom the manufacturing at the fuel elemente.
We authorise Transnuclear. Inc., Rawthorne, N.Y., USA, to app 1v for the relevant !!.R. evnner iteense
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,Ne Date :
n Signature :
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Deputy Geperaljbiraci or Scientific Depdrtmeni.e y
s;..i m e mn.,. $.:5. nu. en. t.
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TEL (Ot)tti 04.11 TFx(03)te0 S.63 TLX88.718 TLG C.ntr. tom SNm.ll.e g
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.CRECKLIST FOR USE IW REVIEW OF REQUESTS FOR REU TO DETERMINI l
TECIDtICAL AND ECONOMIC JUSTIFICATION BR2 REQUEST 1
L l' Name of reactor and facility : BR2 2, Location i le1gian Nuclear Research Centre (C.E.R./8.C.R.)
l l-2400 MOL = BELOIUM
- 3. Quantity of uranium requested (kg U) : 25.10 kg U,,
g b
- 6. Type of fuel element and form of uranium :
i Assembliae of. concentric cylindrical tubes, where the fuel is under the form of UA1, powder.(x e 3), 1.27 gU/ca' aimed with aluminium and i
bunable poisone added ae powder.
i L
- 7. Current reactor power level (MW th) :
Current roaster power 60 to 100 Wth depending on the experimental leading.
Maximal reactor power 125 MWth Current maximal heat flux : 470 W/cas Maximal nominal heat flux : 600 W/ene
- 8. Duty factor i oss appendix 1.
Average burn-up : a) of a load, and of cycle if 6 to 7 $ of arperimente : 37 I b) of eliminated fuel elements : 54 2 4 1
- 9. a) Current core loading (kg U-235) :
8 to 12 ks U-235, depending on the experimental loading 6Ei%
wdN p*A pIPAnc#7AQA THf47*>4 HRW LAW A7 t II f%. CA Wf
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l b) Amount of fuel per element (kg U-235) :
1 400.3 U-235 for a standard fuel element i
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c) Number of elemente in core :
4 L
27 to 40, depending on the esperimental load
)
d) Average core life : One fuel element serves for 10 running weeks.
1.e. 5 cycles of 2 weeks e) Active core and reflector dimensions height
, 914 as
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diameter 1100 as hexagonal lattice 96.44 as pitch fuel active height 726 na f) Neutron flux :
4 h(t).al,E YN' s.
e.I !> V Central Be plug 9 1014 n/ca e 1.4 1014 n/ca's s
Standard fuel element s 3.8 1014 n/ca's s 7 1014 n/ca,
s Driver fuel element (f 200 as) 7 1014 n/ca's 1
- 10. Annual fuel usato (kg U-235) :
Routinely, 75 fuel elements type Vin, or 30 kg U-235.
'In case of development of the safety progrenne for fast reactor i 1 fuel element # 200 an or - 2 kg U-233.
In case of starting of the fusion programme :
20 fuel elements type Yn or 7,2 kg U-235.
- 12. Plans to incaranse, decrease reactor power level I We continuously optimise the reactor puformances : specific and total power, energy produced, number of fresh fuel elemente to be used for an taposed cycle length, taking into account the experimental loading. The present trend is to increase the available fast flux and consequently the specific power, maintaining the nazimum thermohydraulic characte-ristics of the reactor.
- 13. getimated annual supply of current fuel request : 33 kg U-235 minimum.
wEa awUw gag e.T 7mmt* /(*7th0S Pb4 l"J'F"1bd LJOIam er3 % e 07e?? M M LMP
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- 14. Required manufacture's working stock, if any, inchied in this requests The manufacture's working stocke are not included in this request I the manufacture's working stock will be sero on July 1891.
- Por a normal order of g standard fuel elemente, the manufacturer reautres the availability of 27 R3 U-235 above the quantity necessary for the production ((100 x 0.4 Es) + looseeJ.
- 15. Fabrication lose, if any, included in this request (kg U-235) : 22 included in this request.
]
COGDIA 37-4 F-78141 V411sy Franca,
- 17. Fabrication of fuel CIRCA Romans-sur-Istre, France.
Let us note that A.R.A.= Technology (Dounresy-Scotland) intends to fabricate test fuel elemente to be irradiated in the 512 reactor.
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- 18. Inventory on October 31, 1989.
1 The complete inventory is given at appendia 2. Find here the detailed items of this inventory concerning available fuel for the reactor 512.
t Localisation U
U-235 Enrichment Remark l
g
[k 3 Cks)
C-3 S
9 C0CEMA (France) 4 scraps 22.643 20.733 0.9156 a) to be recovered, not available.
last supply 4.482 4.175 0.9315 a) to be converted, not available.
DDR06 (Franes) 88.394 81-091 0.9175- ' 6) Avatiable DOE (USA) 0 0
BR2 (CEN/SCK) 52 fresh fuel alements 22.432 20.868 0.9302 b) usable 21 epecial type 5.321 4.784 0.8990
' b) not usable 10 for experiments 3.926 3.650 0.9295 b) not usable 174 usable spent fuel 54.318 45.607 0.8396 d) i l
l l
Remarks a) Scraps and UF6 to be converted, b) fabricated unitradiated stored fuel.
e) unitradiated non-fabricated fuel.
d) opent fuel stored.
- 19. Date at which the available and usable inventory will be expanded April 1992.
Date at which current inventory, including a, be, c (usable) yill be expended : Teb. 1993.
- 20. Dato current requested fuel will be needed at reactor :
mid 1991.
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31 Date outrant requestsd fusi olli be useded by fabricator i Uct.1WU.
The scraps to be recovered by C0CENA are not available and may be not i
available by afd 1990 at cR1tch iAen another order,# 100 fuel s&ensats has to be issued. The requested 25 kg REU are needed to maintain, in any
)
ease, the necessary NEU-quantities (including the M kg Ett rolling stock at CIRCA).
- 22. Time taken for shipment from USA to converter / fabricator a) land ties for ordering in Un, sia muuths.
b) ohipment in and from USA : six months.
c) conversion UFO
- U-untal : twelve months.
- 25. Date at. which current requested fuel will be expended 1.e.,
when a j
further HEU supply will be needed at reactor and 1992.
The current date ahoduled for the replacement of the laryllium matrix is mid-1995, which will cause nine months approntantely a one year shutdown.
j
- 24. Dates at which reactor could be converted to 45 I fuell to 201 fuel, including time required for licensing procedure :
No dets is fixed yet for BR23 in routine, it will not be before several years, as for other high flux reactors : ATR, NFIR, RyR in Cronoble...
8 U/ca ) are From what we know, teste of fuel plates U 51 -Al (5 4.8 5 3 2 satisfying and the industria11sation of the process is in under way. For j
the future (at a time still to be defined), it would be possible, if requested, to use MEU (45 I enrichment) at the 3R2 reactor. The time required for licensing procedure is equal to a successful irradiation campaign and post-irradiation exanination of prototype fuel elements, increased by six months for reports, when the reprocessing of this fuel has been demonstrated feasible technically and eccnomically. The use of LEU in BR2 demands the availability of fuel plates containing U 81 -Al (3 3 3 7.1 3 U/ca'). No prevision can be given concerning the reliability of this fuel, which is required in order to attain the density level of LEU required for the ER2-reactor.
- 25. History and dates of previous REU supplies by the U.S. : Continuously, since June 08 1959, has U.S. supplied HEU for the reactors 3R2, BR02 and third parties.
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& Si % SwS ee e e.t Semene ee9 mom I"wA t7 "bl kJOt th 1.r2W%t 47*TT fM. CA LNP
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=6-The last delivery of $0.6 kg REU (contract...) for which the licence XSKN-02444 was issued has been shipped from USA to gurope in October 1989. This quantity is splitted in 46.118 kg U-235 metal and 4.482 kg U-235 in the form of UF6.
The metal was directly delivered to CERCA whereas the UF6 was delivered to COGENA for conversion (product not available before October 1990).
The BR2 reactor has reduced its stock of available U-235, reducing the stock of partially burnt fuel element at minimum and recovering all scrape considering the increase of the number of planned esperimente, an annual supply greater than 30 kg U-235 is foreseen after the year 1990.
The appendix 3a, 3b and 3c give the detaile concerning respectively the deliveries of U-235, transfer of fuel for reprocessing and supply to third parties.
- 26. Amount of fuel of U.S.-origin previously consumed during operation of reactor :
The total amount of uranium received up to Oct.
31, 1989 is 1.196.630 kg U-235.
The total amount of uranium burnt to Oct. 31, 1989 is : 1.24 3 U-235/HWd x 349.843 mwd a 0.97 = 420.791 kg U-235.
The appendin 3d gives the total balance of highly enriched urantun received at BR2.
- 27. Status of cooperation between reactor operator and Argonne National 1,eboratory in reduced enrichment program (RERTR) :
We have maintained the contact with the ANL represientatives, for colla-burstion la the RERTh program, altR60th there is some delay in the testing of very high density fuel plates. We cooperate also closely with the fuel fabricatore mainly on the performances of our fuel elemente (fission products relsene, corrosione cladding, behaviour,...).
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- 23. Statue of agreement between reactor operator and ANL to reduce antich-ment t
?
4 Agreemente and soumitments for a joint study between the Belgian Nuclear Research Centre and the Argonne National Laboratory (RERTR progrea) on the utilisation of 1.EU fuel elemente in the 3R2 reactor are effective :
contract signed January 22, 1985. The first phase of the program has
{
demonstrated the - theoretical feasibility for irradiation of a LEU fuel J
elonent test in the 3R2 enre and has been terminated with the first l
approval by the tafety Authorities, by the presentation of the Safety Analysis Report at 8th March 1980. The resserch on technical feasibility I
is in progress. The analysis of this test will assese the modification in the performances and in the.eafety. with corresponding econcate in-l plications. The schedule for 512 test alonente is given at appendix 4 i
- 29. Statue of cooperation between reactor operator and IAEA reduced progras :
The Belgian Wuclear Research Centre as reactor operator participates regularly at the consultant's seating organised by the IAEA for the reduced entiehnent program.
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APPEND 11 1 I 8. Actual and foreseen duty factor.
i ACTUAL FORESERN 1987 1988 1989 1989 and 1990 (2)
Mintaus required date'of begin 18 Dec. 86 16 Dec. 87 15 Dec. SE; 12 cycles of 14 days
& ate of end 16 Dec. 87 15 Dec. 88 19 oct. 89
+
sad of cycle 13/87A 13/84A 11/89A 1 special campaign 3
time of the year (day) 362.7 363.3 307.4 363 operatingtig)
(day) 180.2 167.6 154.2 182 i
duty factor 0.50 0.46 0.50 0.30 l
energy produced (NWd) 11.898.2 10.958 9713
- 12000 number of fresh fuel elemente loaded 75 68 68 80
- 75 mass of fresh U-235 [kg) 28.1 26.9 26.8 31.6
- 30 l
Remarke :
- 1. The operating time is defined to be the time when the reactor has a power
> 80 I nominal power for normal cycle and > 1 I nomine1 power for special campaign.
i
- 2. The required operation has to produce radioisotopes with a sheduled programme determined by a minimum of 12 cycles / year, each with a minimum energy produced of 900 mwd. At least, one special irradiation campaign completes the normal irradiatinn pengre w of each year 1789 and 1990s in the year 1989 the special campaign H0L 7C is equivalent to a routine cycle. During the year 1991, the reactor will operate continuously with 3 in-pile loops (light water pressurised) and will increase its duty factor.
- 3. During all the year 1988, the reduction of U8 fuel delivery resulted in fresh fuel shortage which reduced stroagly the stock of partially burnt (high reactiva) fuel elements.
P1200$/E2090 nt:N3ZW HEWD KDfN 62:IT 06, SO N0f mas-
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.s AFPENDIX 2 l 18 : Inventory on October 31,1989 (and of cycle 11/89 A) teselleetten V
U 238 Bnrishment Resorte bit) b3 0D0914 (France) not evettable eerspe of NUERM 1.022 6.SM 93.03
- e. to be recenrod eerste of CERCA 7.100 6.S$0 91.97
- e. to be resenrod sorspe of m 2 BR01 8.521 7.670 90.01
- s. to be reeevered Suraten UF6 4.442 4.178 93.18
- c. to be converted S RCA (Franse) eve 11able fabrication stock 11.433 16.256 92.30
- c. usable Buretse U-estal 44.114 42.999 93.15
- c. usable Spenten fuel ***
24.643 21.074 St.76
j CEN/93 (Hel Belgius) 911
- Miytite 4996tteent Cit 43 0.111 91.33
- 4. for espotistats et El IR02 41 fuel elemente 18.241 11.997 89.45 be only for BR02 Skt 2 fresh fuel el. type 0 V1n fres 3202 0.891 0.004 90.17
- b. usable 50 fresh fuel e1. type c V!n standard 21.$41 20.064 93.14
- b. usable 10 fresh fuel el. type 0 Vn 3.926 3.650 92.98
- b. for emperimente 21 fresh fuel el. type A S.321 4.784 09.90
- b. not usable
- 173 pett1811y burnt fuel el. 9 84 su 53.915 45.245 43.91
- b. usable **
2 porttelly burnt fuel e1. f 200 mm 2.197 1.902 86.56
- d. usable 49e opent fuel et. 9 84 as 120.044 96.976 75.73
- d. not usable 11 spent fuel el. f 200 sui 15.979 12.961 81.11
- d. not usable l
3R2 BR02 to be recovered i
30 fuel et, type le 4.929 4.335 49.76
- 4. to be recovertd L
1 low burnt fuel el. f 200 am 1.931 1.74 2 90.10
- d. to be recovered Itamarks :
- a. ecraps,
- b. fabricated unitradiated stored fuel,
- c. untrradiated non fabricated fuel.
- d. spent fuel stored.
I.
s,
- only usable to restart the reactor after a
prolongated shut-down (8He-poisoning).
- permitting to produce 8715 Wd.
- preliminary data
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A P P I N D.! I 2 (continued) l
- =
Usable-partially burnt fuel elemente at SR2 The partially burnt fuel elemente are considered usable at 312 when the fuci elements sten't damaged or don't release fissite products and when i
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Uranius content is higher then 200 g U-235 per fuel cell; this latter i
condition means that a fuel element containing less than 200 g U-235 is less reactive than a goryllium plug in a cell neighbovring the core confi-j suration of 30 fuel elemente routinely used.
The listed " mwd usable" to the difference of reefdual U-235 and 200 g U-235 per fuel element, divided
'by 1,24 U-235/MW4.
First one gegend batshe of partially burnt fuci elemeule att more teettive than fredh fuel elemente containing burnable poisons: the actual stock of these fuel elemente le at the minimum level required for a good management.
Accumulation of fuel elemente burnt at 40 I is due to
- 1) small stock of reactive fuel elements.
)
- 2) small core configuration doesn't permit to irradiate all 40 X burnt fuel elemente.
(
I
- 3) firadiation conditions of experimente positionned it. fuel elements type 0 05 and in the usighbouring celle.
burn-up type n
U-tot U-235 U-235 U-235 mwd fresh fresh burnt usable usable
<15 2 6n,61 16 6870.58 6387.66 726.08 2461.58 1985.15 Sn 8
3141.42 2916.59 166.75 1149.84 927.29 L
i
<30 I 6n,61 21 9026.29 8374.42 1971.52 2202.90 1776.53 I
5n 16 6301.46 5834.43 1522.04 1112.39 897 09-h
<40 X 6n,61 33 14187.47 13158.25 4775.46 1782.79 1437.73 l
Sn 18 7043.95 6548.51 2208.23 746.28 601.84
<50 2 6n, 61 26328.98 24360.5R 10971.47 1189.11 P59.96 total 173 72899.85 67580.44 22335.54 10644.89 8584.59
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APPEISIX 3s SWFPLY OF BIGH ENRYC M D UBASIUM M R BR2 m i
i REF.
Contract Order Reference Date 5
/g U
/g.
E' EURA14NE Beception i
1 1
S-es-7 for reacter ame2 08.06.59 4.091 3.675 89,83 i
i 2
BE/IE./4
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E 192/1 30.10.59 40,208.24 36,128.52-99.93 to l
26.10.62 j
3 EU/ML/3-2 EK 293 M 102a 23.12.63 44,267.30 39,776.77 89.93 N
to 1
25.06.64 m
i y
4 EN/IE./3-4 EK 294 E 102b 26.08.64 2I.258.50 19.104.67 09.87 to j
5 30.09.64 N
5 ED/IE./1-22 B1 292 M 101c 26.11.63 22,239.00 19,975.00 99.82 d
10,871.10 9,772.66 39.98 l M 102d 23.05.64 6
EU/DE./3/16 EI 324 l
to l
5 28.09.64 1
r i
w 7
EW/IE./3-21 A,
965.611 M 102e (IAst) 01.01.68 13,755.00 12,375.00 87.97 l t.
o M 102o (CEN)
Of.07.69 l
g 8
EU/IE./3-18 EX 333 E IO2f 04.09.64 9,444.00 S 509.00 98.10 i
i 1
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--______m..______m_.__._____.____,_________.,_______._.__.__.mm.
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SWFFLY OF HIG WETGED WRANN M EE2-REAC10E
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REF.
Contract Order Reference Bete W
/g S
/g 2
EUR&1tBI Reception Enri ammas i
i 9
ED/EL/3-44 EK 333-bis AC 102g 04.09.64 45,500.99 49,917.99 39.93 10 N/IE./3-45 am 1008 AC 102h -
31.05.65 14,692.12 13.298.64 39.99 to 09.09.65 11 W/DE /3-51 am 1012 AC 1021 23.03.66 52,000.00 46,767.00 99.99 3
to 13.04.66 o
4 12 E5/IE./3-63 CON /sa/006 AC 102J 06.02.67 8,996.00 6.969.00 39.69 3
to S
13.03.67 15.a=7.oo 12,54o.co s9.e9 13 EU/DE./3-78 as/1012 AC 102k 07.07.67 22.14.,.08 15,927.00 89 82 3
9 NER2-ter 5
14 EW/IE./3-94 as/1012 AC 102k 24.02.64t 9,696.99 E,707.00 39,99 2
NM2-ter U
15 EU/ML/3-116 I
866.099 AC 1021 93.02.69 56,475.00 5C,551.09 89.51 i
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e SUFFt.Y OF BIG EBRICMD UEANTIBE FOR BR2-MK18R t
l yg/g E
j REF.
Contract Order Beference Bote W
/g U
EURATEBt Beception Eburfladueest 16 EW/Is./3-131
% 5.297 M 192m 02.07.69 13.994.00 12,599.00 99.96 17 EU/WL/3-134
% 5.403 M 102m 02.07.69 6.984.99 6.279.00 89.91' 18 EU/bE./3-101
% 5.612 E 102p 11.09.69 4,600.99 4,133.00 99.84 19 ED/bE./9-1
% 5.976 E 102q 31.12.69 41,997.08 37,823.80 99.06 20 EW/IE./3-21B 165.961 E 102r 01.01.72 3,845.00 3.459.00 99.97 21 EW/IE/9-25 165.528 M 102s 02.98.71 30,;00.00 45,125.00 98.87 12.09.70 55,493.00 49,949.90 96.98 22 AT (49-14) 065.950 uns/Es/17 g
26.05.72 166,574.es 159,e69.e9 e9.s7 3
23 AT (49-14) 166.079 E
ses/ m 35 t
24 m/w./9-11 m 102e Ot.01.73 4,e42.oS 3.64e.e6 9e.e5
.1 l
4 t
Od
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l
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L' SUPPLY OF BIM EMICINED UEANION 70E BE2-EEACTOR 4
REF.
Centract Order Beference Date U
/g U
/
g$ g Z
l EWEAftNt Reception Enriches i
l l
25 E5/bs./3-21 AG 102ts 01.07.73 14.203.00 12.050.00 09.97 26 OE5/ED/7 365.457 20.12.73 97,006.00 99,410.00 93.12 i
2 27 OES/EU/105 ACT/01/105 19.12.74 97,650.00 99,961.00 93.15 l
20 UES/EU/144 15.07.77 76,123.00 70.951.00 93.21 G
j g
29 AG 1438 23.10.00 113,000.00 105,270.00 93.09 i o
i 3a eEs/Eurist as 2osi 20.02.06 55,054.es si,3n.00 93.22l 31 AC 2218 21.10.00 42,744.00 39,024.00 93.17 '
h a
32
- oedered Spanish
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feel (US origin)
> dec OS 24,326.00 21,074.00 09.92 '
i h
33 '
- Licence, f
3
. u 2444 i
i 3
- ELRAInst u-metal
- 02.10.09 46.110.00 42,959.00 93.15 l h
t
- EOtATBN OF6
- 02.10.09 4,402.00 4,175.00 93.15 c.
1^
3 TorAL 1,309.705.00 I,194.493.00 91.20l E
1 0
9
- provistamal value.
E, I
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f e
i APPBBIX 3b PUBL IN EUr REPRDCESSIBC Rep.
Transfer Number Beyrocessfag C,g/g 235 tot 235 5
8 8
8 FresBt PresIn Best Best g
1 1967 125 Burochende 32,133 28,877 24.999 20,332 2
27.03.68 144 Eurochemic 38,372 34,3ee 28,244 22,430 3
06.12.68 300 Eurochemic M,921 24,R95
,lr 16.01.69 50 Nerochemic E3,287
_11,968
- y 27.02.69 150 Eurochemic 35,853 32,2 %
l8 20.03.69 100 Beroebemic 25,934 23,512
!4 01.10.69 150 Eurochemic 37,922 34,099 196,588 34,M5 l
4 30.10.70 130 Berechemic 39,367 35,368 12.02.71 150 Eurectnemaic 37,906 33,938
%,172 44,638
- g I3 5
01.07.72 150 Barochemic 32,367 i
29,07I 23,949 19,953
'E 5
6 E-13.io.72 100 B. roes.sede 2s 253 23,559 19,59e -
is.een s
28.06.73 150 EurocInemic 43.208 38,8B65 29,gt5 22,975 l-7
!3
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i
=
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g
- 3
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- E
8 FWEt, IN EDT Rgymarvssing i
i Rep.
Transfer Number Reprecesslag U
/8 v
/8
- w /8 s
I tM 235 m8 of Elm.
4 I
8 05.02.74 150 Eerschemic 55,375 49,005 37,les 28,221 i
i 9
24.01.75 a50 Mar:oule 59,988 53,934 38,5de 28,631 le 31.12.75 75 Iter:eele 31,139 27.996 19,3I1 14,8N 11 I sen 79 144 Seven==h 47,611 42,993 30,268 22,411 Riv2r Plant
- o fk 12 2 sen 79 144 Savannah 61,938 54,412 37,300 27,421 ig 1 sem se River Flaat 13 2 sen 80 106 Seym===h 47,715 43,193 28,341 20,311 l
to River Flant 1 sen 82 a
E 14 24.11.82 36 ICFF-Idaho 15,468 I4,267 9,531 7,255 5
i' l j 15 2-1989 pending 144 Sewammah 62,157 57,612 35,452 26.SN I ;
=
i 770,668 696,475 523.054 403,641
\\ -
t c,
3 8
llE 1
l l
l
.o SUFFLY OF WRmitNF 79Est M219 TWIES PARTIES 3e
/g Contract Customer Befersace W
/g 5
2 l
m/nl. 9-1 run m/wt/3-123 AC EUR. 24.09.70 200 180 j
NUKElf 23.02.71 4
l UES/EU/7 IRE SCK + IEE 07.03.74 322 300 i
i_
F,5.F.C.
12.08.74 i
UES/E5/35 PTB BrWig FBFC & SCE 20.03.74 234 211 3
Wits /EU/105 IRE NUEBt 16.09.75 12.097 12,919 g
CFK/SCK 05.07.77 I&
NOKDE 15.01.79 4
3
-l 8
UES/EB/7 Metallurgie SCE & EDEIBt 06.11.75 1,803 1,732 l,
MUEBt i EWE O2.04.76 i [
3 E
DES /EU/7 NUEEBE NUEEE A EUR 09.01.76 4I9 3 77 g
NuKIst & SCK 11.02.76 5
UES/W/[44 IEE CEN/S K 28.03.79 3,000 2.790 9
7
~AG I418 BE3 (NWEDO rearralte as 305 21.01.s2 11.005 10,309 E
g AC 2041 MDL7C-Karlsruine (user) leet in 1975 6,608 6.227 0
5 w ral.-
x,72s m,n6
. i
-9 c-i k
i AppENDIE Sd Total balance of highly enriched uraniva from inventory dated October 31. 1989.
$-235[ks]
TOTAL-fresh supply (see appendix 3a) 1194.493 a) Stock at 00 GENA 24.908 at CIRCA 81.091 at BR02 and 812 to be recovered 6.076 at 3R02 only usable at BR02 11.497 at 3R2 type G 6n fresh usable 20.868 at 312 type G Sn not standard 3.650 at 312 type A en.5n no poison 4.784
)
at 822 type C 6n.5n burnt usable 45.244 at 3R2 totally burnt diam. 84 sm 96.976 at BR2 burnt fuel ATR diaa. 200 mm 14.863 at BR1 for experimente O.222 subtotal 310.581 b) Supply to third parties 34.161 c) being reprocessed 403.641 d) burnt 349.843 Wd x 1,24 g/Wd x 0,97 420.791 e) fabrication losses until Oct. 31, 1989.
16.704 TOTAL 185.877 difference 8.615
'i:
-.i 0$.
This difference is lower than 2 % of the mass correspending to the energy produced and the fabrication losses.
.sa e.vme re pat lln rmar37% WOI.m 1.r2W%l FC
- T T M.
M LW
=.19 -
j 0
l AFFRNDII 4 i
4 8 28. Approntaate schedule for 3R2 test elemente at November 1989.
I Approximate time Approminate completion required (monthe) date
- 1. First approval of Safety Report.
Bth March 1988
- 2. Finalise detailed specification 16th April 1989 i
t
- 3. Fabrication feasibility reports from CIRCA and 2nd approval of Safety Report.
tecember 1989
+
- 4. Fabricate test fuel elemente.
12 tecember 1990
- 5. Reactivity and flux measuremente in 3102 Critical Facility 3
January 1991 Third approval of Safety Report.
March 1991
- 6. Irradiation in BR2 18 July 1992
- 7. Cool irradiated elemente.
4 September 1992 8.* Foot-irradiation-examination 3
January 1993 The key uncertainties in this schedule are the date[ for finalisation of the specifications by CERCA and the dates by which C21CA will be able to deliver the finished elements to BR2.;q
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