ML20149E348
| ML20149E348 | |
| Person / Time | |
|---|---|
| Issue date: | 02/05/1988 |
| From: | Peterson M NRC OFFICE OF GOVERNMENTAL & PUBLIC AFFAIRS (GPA) |
| To: | Thorne C STATE, DEPT. OF, BUREAU OF OCEANS & INTL. ENVIRONMENT |
| References | |
| NUDOCS 8802110017 | |
| Download: ML20149E348 (1) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION 5
E WASHINGTON, D. C. 20555 '
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FEB 5 Iggg Mr. Carlton E. Thorne, Director Office of Nuclear Export and Import Control Bureau of Oceans and International Environmental and Scientific Affairs U.S. Departr.ent of State Washington, D.C.
20520 Cear Mr. Thorne:
Enclosed please find a letter from Transnuclear, Inc. which provides additional infomation on export license applications XSNM02144, Amendment 03 and XSNM02359.
Please consider this in conjunction with the original applications which were forwarded to you on October 30, 1986 and December 21, 1987, respectively.
Sincerely.
's y,.
7-Marvin R. PeteYson, Assistant Director for International Security Office of Governmental and Public Affairs
Enclosure:
Ltr. dtd 1/29/88 (XSNM02359-West Gemany)
(XSNM02144, Amend 03 -Belgium) 9002110017 080205 PDR XPORT X5NM-2144 PDR
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I ysymoD MV db January 29, 1988 U.S. Nuclear Regulatory CmInission One White Flint North l
11555 Pockville Pike bhil Stop hTl/3-H-5 Pockville, thryland 20852 Attention: Mrs. Betty Wright O
Fe: Export License Application XSNM2144 (BR-2)
Export License Application XSN'42359 (THTR)
Dear Mrs. Wright:
We are enclosing the follcwing data on the above referenced licenses:
-XSNM02144: Original copy of the reactor check list. (A copy of the reactor check list was mailed to you January 14.)
-XSNM02359: Original copies of the end use state: Tent and reactor check list. A copy of the end use statenent and our license application w re mailed to you on December 16, 1987.
Very truly yours,
~
David A. Gray Traffic Coordinator DAG/
Enclosures as stated above 3
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ONE SKYLINE PLACE * $205 LEESBURG PIKE
- FALLS CHURCH. VIRGINIA 22041 3876 TELEPHONE 703-820-2450
- CABLE: TNY UW
- TELEX: 64493 l
L_________..______
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26.11.87 l u, R 0468 1,
%SNM O21W WA.OS i
CHECKLIST FOR USE IN REVIEW OF REQUESTS FOR HEU TO DETERMINE t.
TECHNICAL AND ECONOMIC JUSTIFICATION BR2 REQUEST The checklist of the BR2 request, dated October 20 1986, is revieved acccrding to the meeting held at MOL-Belgitm the 20 October 1987, where W!.
J. MATOS (ANL), A. BEECD!ANS and H. LENDERS (CEN/SCK) vere present.
The revieved checklist is edited Nove :ber 26, 1987 and 4 appendi: are attached.
- 1. Name of reactor and facility : BR2
- 2. Location : Belgian Nuclear Research Centre (C.E.N./S.C.K.)
B-2400 MOL - BELGILH
- 3. Quantity of uranium requested (kg U) : 42.9 kg U g g.
- 4. Enrichment in the isotope U-235 : 93.3
- 6. Type of fuel element and form of uranium :
Assemblies of concentric cylindrical tubes, where the fuel is under the 8
form of UAl powder (x : 3), 1.27 gU/ cm, mixed with aluminium and burnable poisons added as powder.
- 7. Current reactor power level (HW th) :
Current reactor power : 60 to 100 MWth depending on the experimental loading.
Maximal reactor power : 125 MWth 2
Maximal nominal heat flux : 600 W/cm
- 8. Duty factor : see appe'ndix 1.
Average burn-up : a) of a load, end of cycle 37 g if 6 to 7 $ of experiments :
b) of eliminated fuel elements : 54 + 3 %.
'I b
s
e 26.11.87 R 0468 2.
- 9. a) Current core' loading (kg U-235) :
8 to 12 kg U-235, depending on the experimental loading b) Amount of fuel per element (kg U-235) :
400 g U-235 for a standard fuel element c) Number of elements in core :
27 to 40, depending on the experimental load d) Average core life :
One fuel element serves for 9 running weeks, i.e. 3 cycles of 3 weeks e) Active core and reflector dimensions :
height 914 m=
diameter 1100 mm hexagonal lattice 96.44 m pitch a
f) Neutron flux :
oo ef tV f cge).a s o).a
,' s s
'0,i Qt V 9 10 'n/cm s 1.4 1014n/cm,
1 a
2 Central Be plug 1
2 l
2 Standard fuel element 5 3.8 10 'n/cm,
g 7 10 'n/cm,
l 2
7 10 'n/cm,
Driver fuel element (G 200 mm)
- 10. Annual fuel usage (kg U-235) :
Routinely, 60 to 75 fuel elements type vin, or 24 to 30 kg U-235.
In case of development of the safety programme for fast reactor :
I fuel element 9 200 mm or - 2 kg U-235.
In case of starting of the fusion programme :
.20 fuel elements type Vn or 7,2 kg U-235.
- 11. Annual spare fuel regtfirement (kg U-235) :
One year operation + so=e special fuel elements total :
40 kg U-235
- 12. Plans to increase, decrease reactor power level :
We continuously optimize the reactor performances : specific and total power, energy produced, nu=ber of fresh fuel elements to be used for an imposed cycle length, taking into account the experimental loading. The present trend is to increase the available fast flux and consequently the specific power, maintaining t't e maximum thermohydraulic characte-ristics of the reactor.
26.11.87 sg R 0468 3.
l
- 13. Estimat7 annual supply of current fuel request :
d For commercial reasons, we order the fuel every two years (40 kg/ year).
- 14. Required manuf acture 's working stock, if any, included in this request (kg U-235) :
Existing manufacture's working stocks are not included in this request.
- 15. Fabrication loss, if any, included in this request (kg U-235) : 2 %
included in this request
- 16. Names of conveitor : NUKEM Hanau, Germany l
- 17. Fabricato'r of fuel : NUKEM Hanau, Germany.
CERCA Romans-sur-Issre, France l
BABCOCK & WILC0X, Lynchburg VA USA
(*this latter fabricator has withdrawn his offer by letter dated June 27, 1985).
e
26.11.87 R 0468 4.
- 18. Inventory on October 2, 1987.
The complete-inventory is given at appendix 2. Find here the detailed items of this inventory concerning available fuel for the reactor BR2, A.-Scraps and fuel plates to be recovered by cold reprocessing.
Localisation U
U-235 Enrichment Remark g
[kg)
[kg)
[ %)
CERCA (Romans) fuel plates 7.100 6.530 91.93 (b)
BR2 (Mol) 32 fuel elements not useable 8.008 7.205 89,97 (b)
LABO SCK-CEN (Mol)
,e reception samples 0.563 0.509 90.41 (a)
Total 15.671 14.244 B. Available and useable fresh fuel elements at BR2.
Localisation U,g U-235 Enrichment Remark g
[kg)
[kg)
[ %)
NUKEM (Hanau) fabrication process 7.277 6.511 89.47 (c)
CERCA (Romans) fabrication process 17.881 16.434 91.93 (c)
BR2 78 fresh fuel elements 33.102 30.394 91.82 (b)
Total 58.260 53.339 Remark : a) Scraps.
b) fabricated unitradiated stored fuel, c) unirradiated non-fabricated fuel, d) spent fuel stored.
f
-26.11.87 R 0468 5.
- 19. Date et which the available and useable inventory will be expended :
Augur-1989.
Late at which current inventory, including a, b, c (useable), will be expended : February 1990, on the base of use of 27 kg U-235 in fresh i
fuel clements per year, assumption made that the fuel elements coming from BR02 don't release fission products and the experimental loading has being. maintained minimum.
- 20. Date current requested fuel will be needed at reactor :
Mid of 1988, taking into account one year ope ation spare.
- 21. Date current requested fuel will be needed by convertor and fabricator :
End of 1987.
- 22. a) Time taken for shipment from USA to convertor / fabricator : Six inonths b) Lead time for ordering in USA :
Six months 23.'Date at which current requested fuel will be expended i.e.,
when a further HEU supply will be needed at reactor : Mid 1991.
- 24. Dates at which reactor could'be converted to 45 % fuel ; to 20 % fuel, including time required for licensing procedure :
No date is fixed yet for BR2 ; in routine, it will not be before several years, as for other high flux reactors : ATR, HFIR, HFR in Grenoble....
8 From what we know, tests of fuel plates U Si -Al (5 4.8 g U/cm ) are 3 y under way in many places and the industrialization of the process is in preparation. For the future (at a time still to be defined), it would be possible, if requested, to use MEU (45 % enrichment) at the BR2 reactor.
The time required for licensing procedure is equal to a successful irradiation campaign and post-irradiation examination of prototype fuel elements, increased by six months for reports.
The use of LEU in BR2 demands the availability of fuel plates containing 8
U Si -Al (i: 7.1 g U/cm ).
No prevision can be given concerning the 3
g reliability of this fuel, which is required in order to attain the density level of LEU required for the BR2-reactor.
- 25. History and dates of previous HEU supplies by the U.S.
- Continuously, since October 30 1959, has U.S. supplied HEU for the reactors BR2, BR02 and third parties. The last delivery of 51.322 kg U-235 (contract Ag 2041) was shippcd February 28, 1986 to bTKEM : the appendix 3a, 3b and 3e give the details concerning respectively the deliveries of U-235, transfer of fuel for reprocessing and supply to third parties, b
i
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1 2's!;
6.
)
1
- 26. Amount of fuel of U.S.-origin previously consumed during operation of reactor :
The total amount of uranium received up to October 2,
1987 is :
1,081.949 kg U-235. (see appendix 3c)
The total amount of uranium burnt to October 2,
1987 is 1.24 g U-235/Wd x 327,280 Wd x 0.97 = 393.652 kg U-235.
The appendix 3d gives the total balance of highly enriched uranium received at BR2.
- 27. Status of cooperation between reactor operator and Argonne National Laboratory in reduced enrichment program (RERTR) :
We have maintained the contact with the ANL representatives, for colla-boratict in the RERTR program, although there is some delay e in the testing of very high density fuel plates. We cooperate also closely with the fuel fabricators mainly on the performances of our fuel elements (fission products release, corrosion, cladding, behaviour....).
- 28. Status of agreement between reactor operator and ANL to reduce enrich-ment :
Agreements and commitments for a joint study between the Belgian Nuclear Research Centre and the Argonne National Laboratory (RERTR program) on the utilization of LEU fuel elements in the BR2 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 l
element test in the BR2 core and will be te rminat ed with the first approval by the Saf ety Authorities, by the presentation of the Safety Analysis Report before the end of 1987. The research on technical feasibility is in progress. The analysis of this test will assess the i
modification in the performances and in the safety, with corresponding I
economic implications. The schedule for BR2 test elements is given at appendix 4.
'9.
Status of cooperation between reactor operator and IAEA reduced pro-l l
gram : The Belgian Nuclear Research Centre as reactor operator partici-1 pates regularly at the consultant's meeting organized by the IAEA for the reduced enrichment program.
l
o 26.11.87 R 0468 7.
APPENDIX 1 5 8.
Actual and foreseen duty factor.
6 ACTUAL FORESEEN 1987 1987 1989 minimum minimum date begin 18 dec. 86 prevision prevision date end 2 oct. 87 13 cycles 10 cycles end of cycle of 14 days of 14 days 10/878 operation operation time of the year
[ day 3 287.0 3n5 365 O}
II operating time
[ day) 139.7 182 150 I
duty factor 0.487 0.50 0.41 energy produced
[Wd )
9096.2
-12000
-9000 (O
nu=ber of fresh fuel elements loaded 57
- 78 60 to 75 mass of fresh U-235
[kg]
21.4
~ 30 24 to 30 Renarks :
- 1. The operating time is defined to be the time when the reactor has a power > 80 % nominal power for normal cycle and > 1 % nominal pcwer for special campaign.
- 2. At least, two special irradiation campaigns will cceplete the n'ernal irradiation program:ne of the year 1988 ; these special irradiation campaigns will occur durir.g the foreseen shut-down periods.
- 3. Due to the 'He poisoning of the beryllium matrix, the shut devn period is limited to 28 days (year 1988) and 21 days (year 1992), when the reactor eperates routinely at 120 % nceinal power during 14 days with the actual radioisotope loading, producing 900 Wd per cycle ; consequently the minimum energy produced in one year may not be Icver than 8100 Wd (year 1988) and 9000 Wd (year 1992).
- 4. The minimum prevision 9000 Wd er 24 kg U 235 may avoid Beryllium matrix poisening and insure the base radioisotopes production. Additional cycles of operation to satisfy the increasing demand of radioisotopes production and several irradiation campaigns for the experimental pro-gramme have to increase the annual energy produced ; therefore the nonnal prevision will maintain 12000 Wd and a requirement of 30 kg of fresh U 235.
l
- W
-26.11.87-R 0468 8.
APPENDIX 2
l 18 : Inventory on October 2,1987.
. Localisation U
U-235 Enrichment Remark gog
[ ks]
[ks)
[s]
NUKEM (Hanau) l fabrication process 7.277 6.511 89.47
- c. useable CERCA (Romans) fabrication process 17.881 16.434 91.93
- c. useable fuel plates 7.100 6.530 91.93
- d. reprocessed l
l BR02 (Mol Belgium) 61 fresh fuel elements 20.130 18.102 89.93
- b. useable only at BR02 BR2 (Mol-Belgium) 32 fresh fuel elements, desaged 8.008 7.205 89.97
- b. to be recovered 18 fresh fuel elements, special type 4.572 4.104 89.76
- b. not useable
- 40 fresh fuel eierents, not standard 11.562 10.661 92.21
- b. for expertments 78 fresh fuel elements, standard 33.102 30.394 91.82
- b. useable 3 spent fuel elements, ATR type 4.189 3.714 88.66
- d. useable 255 spent fuel elements, partially burnt 68.963 59.240 85.90
- d. useable 445 spent fuel totally burnt 128.620 94.110 73.17
- d. not useable LABO (CEN-SCX Mol) reception samples 0.563 0.509 90.41 a, to be recovered 323.644 266.325 Remark i a. scraps.
- b. fabricated untrradiated stored fuel.
- c. unirradiated non fabricated fuel.
l
- d. spent fuel stored, i
- only useable to restart the reactor af ter a prolongated shutadown to compensate the antireactivity of the beryllium poisening.
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SUPPLY OF HIGH ENRICHED URANIUM FOR BR2-REACTOR APPENDIX 3a Rep Contract Order Reference Date U
g U
8 Z
235 EURATOM Reception Enrichment I
HE/Mt./4
?
AG 192/1 30.10.59 40,208.24 36,128.52 89.93 to 26.10.62 2
EU/MI./3-2 BX 293, AG 102a 23.12.63 44,267.30 39,776.77 89.93 to 25.06.64 3
EU/ML/3-4 HX 294 AG 102h 26.08.64 21,258.50 19,104.67 89.87 to 30.09.64 4
EU/ML/1-22 HX 292 AC 102c 26.11.63 22.239.00 19,975.00 89.82 5
EU/MI./ 3-16 HX 324 AG 102d 23.05.64 10,871.10 9,772.66 89.90 to 28.09.64 6
EU/ML/3-21A 965.611 AG 102e (MMN) 01.01.68 13,755.00 12,375.00 87.97 to AG 102o (CEN) 01.07.69 7
EU/ML/3-18 HX 333 AG 102f 04.09.64 9.444.00 8,509.00 90.10
'* U
? -.
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5 SUPPLY OF HICH ENRICHED URANIUM FOR BR2-REACTOR l
1 f
l Rep Contract Order Reference Date U
/g U
/E Z
235 EURATOM Receptton Enrichment 8
EU/ML/3-44 BK 333-bis AG 102g 04.09.65 45,500.00 40,917.00 89.93 9
EU/ML/3-45 aa 1008 AG 102h 31.05.65 I4,692.12 13,208.64 89.90 to 09.09.65 10 EU/ML/3-51 aa 1012 AG 1021 23.03.66 52,000.00 46,767.00 89.90 to 13.04.66 II EU/ML/3-63 CON /na/006 AG 102j 06.02.87 8,996.00 8,069.00 89.69 to 13.03.67 15,097.00 13.540.00 89.69 07.07.67 22,185.00 19,927.00 89.82 12 EU/ML/3-78 aa/1012 AG 102k, NBR2-ter 13 EU/ML/3-94 aa/1012 AG 102k 24.02.68 9,696.00 8,707.00 39,80 2
NBR2-ter 14 EU/ML/3-il6 866.099 AG 1021 03.02.69 56,475.00 50,551.00 89,51
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5 SUPPLY OF HICil ENRICHED URANIUM FOR BR2-REACTOR Rep Contract Order Reference Date U
/g U
/g I
35 EURATOM Reception Enrichnent 15 EU/ML/3-131 965.297 AC 102m 02.07.69 13,984.00 12.580.00 89.96 16 EU/ML/3-134 965.403 AC 102n 02.07.69 6,984.00 6.279.00 89.91 17 EU/MI./3-101 965.61,2 AC 102p 11.09.69 4,600.00 4,133.00 89.84 18 EU/ML/9-1 965.976 AC 102q 31.12.69 41,997.00 37,823.00 90.06-19 EU/ML/3-21B 165.961 AG 102r 01.01.72 3,845.00 3.459.00 89.97 20 EU/ML/9-25 165.528 AC 102s 02.08.71 50,100.00 45,125.00 90.07 21 AT(49-14) 065.950 12.09.70 55,493.00 49,949.00 90.01 UES/EU/17 22 AT (49-14) 166.079 26.05.72 166,574.00 149,869.00 89.87 UES/EU 35 23 EU/ML/9-Il AC 102t 01.01.73 4,002.00 3,640.00 90.05 De
- u*$5
y SUPPL.Y OF HIGil ENRICllED URANIUM FOR BR2-REACTOR Rep Contract Order Reference Date U
/g U
/8 I
235 EURATOM Reception Enrichnent 24 EU/MI /3-21 AG 102u 01.07.73 14.283.00 12,850.00 89.97 25 UES/EU/7 365.457 20.12.73 97,086.00 90.410.00 93.12 26 UES/EU/105 ACT/01/105 19.12.74 97,650.00 90,961.00 93.15 27 UES/EU/144 15.07.77 76,123.00 70,951.00 93.21 28 AG 1418 23.10.80 113,080.00 105,270.00 93.09 29 AG 2041 28.02.86 55,054.00 51,322.00 93.22 TOTAL 1,187,539.00 1,061,949.26 91.11 l
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FUEL. IN HOT REPROCESSING APPENDIX 3h Rap Transfer Number Reprocessing U
g U235 "-
"tot g U
8 235 date of Plant Fresh Fresh Rest Rest Fuel of Elm.
I 1967 125 Eurochemic 32,133 28,877 24,999 20,332 2
27.03.68 144 Eurochemic 38,372 34,500 28,244 22,430 3
06.12.68 100 Eurochemic 26,911 24,195 16.01.69 50 Eurochemic 13,287 11,948 27.02.69 150 Eurochemic 35,853 32.236 20.03.69 100 Eurochemic 25,934 23,512 01.10.69 150 Eurochemic 17.922 34.080 104.580 84,265 4
30.10.70 150 Eurochemic 39,367 35,360 12.02.71 150 Eurochemic 37,806 33,930 56,172 44,631 5
01.07.72 150 Eurochemic 32,367 29,071 23,849 19.053 6
13.10.72 100 Eurochemic 26,253 23,559 19,590 15,691 "E
o-7 28.06.73 150 Eurochemic 43,208 38,845 29,685 22,875 h,~
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FUEL. IN HOT REPROCESSING e
Rap Transfer Number Reprocessing U
g U
8 U
g U
8 235 m
235 date of Plant Fresh Fresh Rest Rest Fuel of Elm.
8 05.02.74 150 Eurochemic 55,375 49,805 37,100 28,222 9
24.01.75 150 Marcoulle 59.981 53.934 38,560.
28,637 10 31.12.75 75 Marcoulle 31,139 27,996 19,311 14.028 11 I sen 79 I44 Savannah 47,611 42,903 30,260
.22,412 River Plant 12 2 sem 79 144 Savannah 61,930 56,412 37,380 27,421 I sen 80 River Plant 13 2 sen 80 108 Savannah 47,715 43,193 28,341 20,313 to River Plant I
I sen 82 14 24.I1.82 36 ICPP-Idaho 15,468 14,267 9,531 7,255
." 2 L
$IO 708,632 638,623 487.602 377,565
e e.
SUPPLY OF URANIUM FROM BR2 TO THIRD PARTIES Appendix 3c Contract Customer Reference U
g U
I 235 i
EU/ML 9-1 FRM EU/ML/3-123 AG EUR. 23.02.71 200 180 NUKEM 24.09.70 UES/EU/7 IRE SCK + IRE 07.03.74 322 300 F.B.F.C.
12.08.74 UES/ Ell /105 IRE NUKEM 05.07.77 12,897 12,015 CEN/SCK 16.09.75 NUKEM 15.01.79 UES/EU/144 IRE CEN/SCK 28.03.79 3,000 2,790 AG 1418 BR3 (NUKEM)
Kontrakt AU 305 11,085 10,309 AG 2041 MOL 7C - Karlsruhe 6,688 6,227 34,192 31,821 Total a
'lt' 4
26.11.87 R 0468
. APPENDIX 3d Total balance of highly enriched Uranium from Inventory dated October 2, 1987.
U-235 [kg]
Total freef pupply US origin 1,081.949 (see appenc ix 3a)
Stock (see appendix 2) scraps and fuel plates to be recovered 14.244 available at NUflM and CERCA 22.945 useable fresh fuel 30.394 fresh fuel special type 4.104 fresh fuel not standard 10.661 spent fuel 157.064 BR02 18.102 Sub-total of stock 257.514 Hot reprocessed (see appendix 3b) 377.565 Supply to third parties (see appendix 3c) 31.821 Burnt : 327,280 mwd x 1.24 g/ mwd x 0,97 -
393.652 Fabrication losses according to the declaration 18.819 of the fabrications Total 1,079.371 The difference between the 2 totals appears to be 2.578 kg, which is less than 1 % of the mass corresponding to the energy produced and f abrication losses.
- i. '
26.11.87 e
R 0468 APPENDIX 4 5 28. Approximate schedule for BR2 test elements at September 1987.
Approximate time Approximate completion required (months) date 1.'First approval of Safety Report.
1-3 December 1987
- 2. Fabrication Feasibility Reports.
1-3 December 1987 e
from NUKEM and CERCA.
- 3. Finalize detailed specification 3
Second approval of safety Report.
March 1988 l
- 4. Fabricate test fuel elements.
6 September 1988 I
I
- 5. Reactivity and flux measurements in BR02 Critical Facility 3
December 1988 Third approval of Safety Report.
- 6. Irradiation in BR2 18 July 1990
- 7. Cool irradiated elements.'
4 September 1990 1
l
- 8. Post-irradiation-examination 3
January 1991 The key uncertainties in this schedule are the dates for finalization of j
the specifications by CES/SCK, NUKEM and CERCA and the dates by which NUKEM l
and CERCA vill be able to deliver the finished elements to BR2.
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Xs&ihaAB59 January 29, 1988 U.S. Nuclear Pogulatory Ccmaission One White Flint North 11555 Fockville Pike Mail Stop WFl/3-H-5 Rockville, Maryland 20852 Attention: Mrs. Betty Wright O
Fo: Export License Application XSNM2144 (BR-2) A Export License Application XSNM2359 (TIfrR)
Dear Mrs. Wright:
We are enclosing the follcuing data on the above referenced licenses:
-XSNM02144: Original copy of the reactor check list. (A copy of the reactor check list was miled to you January 14.)
-XSNM02359: Original copies of the end use state: rent and reactor check list. A copy of the end use statement and our license application were mailed to you on December 16, 1987.
Very truly yours, M
David A. Gray Traffic Coordinator DAG/
l Enclosures as stated above i
- (, a U?.
ONE SKYLINE PLACE
- 5205 LEESBURG PIKE
- F ALLS CHURCH VIRGINIA 22041 3876 TELEPHONE 703 820-2450
- CABLE TNY UW
- TELEt 64493
i i
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HOCHTEMPERATUR-KERNKRAFTWERK GESELLSCHAFT MIT BESCHRANKTER HAFTUNG x
/
GEMEINSAMES EUAOPAISCHES UNTERNEHYEN
-gG. S ele-e.c sva3e > cw sa-
.1 xsamo 2 359 to whom it may concern T WTk m
.:_..e H KWB K-Bo/Gi (0231) 438-2018 Dec. 10, 1987 (VEW)
End Use Statement The enriched uranium to be delivered in two consignments 1989 and 1990 is specified as follows:
260.650 kg U containing 243.186 kg U235 enriched to a maximum of 93.3 percent.
The material will be used to fabricate fuel elements for the Thorium-Hochtemperaturreaktor (lHTR-100-reactor) situated in Ventrop near Ham.m. owned and operated bei HKG.
The material ist coming from the US-00E-enrichment plant arid will be sent to the fuel fabrication company, H0 BEG in Germany. Before it will be converted from UF via U 0 int metal or U 03 8 pr bably 6
38 bei 00E. Subsequently it shall be converted into UtlH by the company flVKEM GmbH.
We authorize herewith the TRAtlSNUCLEAR, Inc., Falls Church, Va.
to call for the export license and to make supplemental declarations to the way and manner of shipping the material mentioned above.
~
HOCHTE'MPERATUR-KERhKRAFTWERK GMBH ihj
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= A.. A-, =.. u.,
a........
3 H KWB K-Bo/Gi Dortmund, January 11. 1988 CHECKLIST FOR USE IN REVIEW OF REQUESTS FOR HEU TO DETERMINE TECHNICAL AND ECONOMIC JUSTIFICATION 1)
'JaTe e!.teastet.and f ag!!!ty THTR = "Thorium-Hochtemperatur-Reaktor" Owner: HKG = "Hochtemperatur-Kernkraftwerk, GmbH, Gemeinsames Europsisches Unternehmen" (Common European Enterprise),
D 4700 Hamm 1, Federal Republik of Germany 2)
Lggag!g:
Hamm-Uentrop, Land North-Rhine-Westphalia, Federal Republic of Germany; Hamm is located at the east part of the Ruhr-district 3) 99aniltz et 9tanige cgggesteg,{gg,ul 260.650 kg U 4)
En[!ghgegt,19,thg,!sgtgge,y235 appr. 93.15 +- 0.15 % U-235 5) ggag}!!y g{,gtanigg,tegges}eg,(Bg,y;235!
243.186 kg U-235 6)
TZ2e,gf, fuel,elegent,and,fgrg,of,uraniug Graphite sphere, diameter 60 mm, containing coated particles.
Uranium / Thorium-oxide kernels 1 : 10. Kernel diameter 400 pm; Codted with PyC o
,,.a u
- %v <
c 7)
Cy((egt,[ gag!g[,gggg[,}eyg},,,,{Gy,th}
- i
[
Reactor is in commercial operation; the operation >
License was obtained on April 9, 1985; full operation since mid 1986.
Current reactor power level: 7 5 0 M'r't h Designed output:
750 MW thermal-308 MW electric net 8)
Outy, factor, average,burnug 3
Outy (load) factor:
74 %
Average burnup:
11.4 % fima 134 % fifa 9a) Current core,1gading,,{kg,U-23!
app r. 220 kg U-235 in reactor (Dec. 31, 1987)-
in this figure is a burn-up of 273 fed taker. into account.
b) Amount,gf, fuel,ger, element,,(kg,U-23 i 0.96 g U-235 10.20 g Thorium t c) fjumber,gf elements,in,cgre (March 31, 1986) l First loadina: 479,818 fuel elements 45,288 absorber elements (containing Boron and Hafnium) 176,610 graphite elements (without fuel) l 701,716 i l l - in equilibrium: l appr. 703,000 fuel elements I
-3 d) Average, core, life 3 years at full load 4 years at 74 % load e) 3gt!yg cgre,g!gggsiggs t
- Diameter, 5.6 m Height 6.0 m f) Uf91C90.fl25 14 2
Average thermal 1,21. 10 n/cm . see 10)'oee9a!.!9el.959as!..Ihg.u:23s! 161 kg u-235 at 74 % load
- 11) 6009al seate,fue,1,teguitegegt,,1t,agy,,(gg,u:23s1 No annuai spare fuel requirement (on load refueling)
J ) i
- 12) glags,se,igstease,,gestegsg,reagtet,e90!C le!!!
No plans
- 13) Estjggtgg,aggua},su221Y.9f.99CCggt,{gg],tegugst Current planned fuel element fabrication is as follows:
for 1988 120,000 elements l for 1989 170,000 elements for 1990 170,000 elements l l l l t l l t
- ,3 -
g[' a s s,, .,C. r I -y i s', 4 / /' j / f w +. / i. 14) Required manuf actura's working stock, 'if any, included in, t h.i.s. r. e. g u..e s t... { k g. U. - 2 3 5. ), The quantity of_HEU requested (260.650 kg U) includes f a manufacturer's working stock of 1.6 % (1.3 % fo losses and 0.3 % f Ur samp1'es) W / y% 15) Fabricatign, loss,if,any3,inc19ded in this request g fabrication loss is 1.3 % 7 ,. / v, 16) Names,gf,cgnvertor,and, fabricator,gf,{uel s Enriched uranium hexafluoride in the form of metal or 0 0 g 3 will be finally converted and manufacturdd-into complete ^4. elements at Nukem GmbH, Nukem is partner in the group, which erects the reactor. In 1972, after sigasture of the contract for building the THTR, Nukem 5ounded the 100 % affiliate HOBEG, Hochtemperaturreaktor Brennelement GmbH, responsible within the Nukem organisation for the fabrication of high temperature fuel elements. In the case of the THTR. elements HOBEG is subcontractor to Nukem. (THTR. order before HOBEG-foundation) 6 17) Location v Hanau, State of Hessia, Fed. Rep. of Germany. Manau ist s located appr. 25 km east of Frankfurt. 4 /. l f ,/ r,r ./ .e ,e e y "ys'n f 1D* i_ ~_
3y ' O' ', g ;[ WY.,) - 'Q' g g,%,. - 4 .. 4 3 '?. .% f;... .[% \\ 1 N lN'4,- v \\ s,., - 5-I' i
- 4..
- -y 18)
Inventgry Fuel in'ventory for THTR-production imported from the USA is 1,081.286 kg HEU corresponding to appr. 1,008 kg U-235 as of Dec. 31, 1987. a) ggagt!tt,g[, scrag,y;23!3,usgag193,ggg;usgaglg,{kg,y23}} /., s , s..
- x..
As per end of Dec. 87 app r. 15 kg HEU in form of scrap. '?s corresp. to appr. 14 kg U-235 ,' y This scrap is useable. No unuseable scrap. x - =.. "s' b) Quanti,ty,gf, fabricated,ugirradiated, stored, fuel,availabig 7 ?
- 1 i y
A~s per end of Dec. 87 s c y ,i n eactor a pp r. 480,000 elements "for reloads appr. 409,000 elements appr.-889,000 elements are manufactured .containing appr. 886 kg U-235 (inclusive the losses , ' ~
- ~.
'1 and samples for irradiation in AVR) / 8 c) Quant'ity of unirradiated non-fabricated stored fuel (which V!31.59_ayajlag}g,((gg,{aggjcatjgg,glagggd.gg,jg gggggssl, Received from the US 00E and GE appr. 1,008 kg U-235 elements manufactured a s per Dec. 31, 1987 appr. 886 kg U-235 l fuel in different stages of fabrication j as per Dec. 31, 1987 appr. 122 kg U-235 L d) Am9unt,9,soent, fuel,stgred,{kg,U-23!1 f ~ Up to now no spent fuel stored. l } s l l
e 6 19) Date at which current inventory, including a, b, c will
- b. e.. e. x. p e. n. d. e. d.............................................
Appr. end of 1988. i. 20) g a g g, g g t t g g 3, t g g g g s !g g,{ g g !,y!!!, g e, g g g g gg, { a 3, t g g g 39 tl Appr. beginning-of 1989. According to the time schedule as per end Dec.1987. 21) Date current requested fuel will be needed by convertor a n. d.. f. a. b r..i c. a..t o. r.......................................... In two consignments, appr. 150 kg HEU January 1989 and appr. 110 kg HEU October 1989. 22a) !!me,[akgg,[gt,sh!ggggg,{tgg,U}3,$g,gggygt}gtf{agtiga}gt less than 1 week; plus at least 4 weeks for arrangements with "Deutsche Luftwaffe". b) Lead, time,f or,orde ring,ig,Uj A 180 days (Utility Services Contract) l 23) Date at which current requested fuel will be expended i.e., VD90.a,[gt}hgt,HEU,syggly,y!!!,gg,ggggeg,a3,tgag}gt,,,,,,,, End of 1990, according to the time schedule as per end of Dec. 1987. 24) Dates at which reactor could be converted to 45 % fuel; 19.29.51.19939Y199.{jmg,tggg!tgg,{gtg}}gggs!gg,gtggggggg The THTR. reactor is the prototype of a power. reactor and not a research reactor. The conclusions of INFCE (Working. group VIII) and the international program RERTR (reduced enrichment in research and testreactors) do not apply. l
e s 7 Moreover with the intension to convert from HEU to MEU or LEU, i.e. conversion of the fuel cycle the whole licensing procedure for the plant would have to be started again from beginning. A change of the core design would r furthermore influence all components of the primary coolant cycle and cause restrictions in reactor operation. This on the other hand would most probably require a new public hearing. 20 a n sgry agg gates gf,gtey!gus,!!Eu suee!!es.by,the,n g r Quantities of HEU already received from the USA for the fabrication of THTR fuel elements are the following: month / year kg U 6/72 48.038 8/72 48.021 11/72 47.997 2/73 16.317 3/73 31.683 4/73 48.083 7/73 48.023 l 3/74 96.025 6/74 63.948 12/74 16.009 1/76 47.949 7/77 103.082 6/78 120.005 from GE 6/84 51.271 l 8/85 51.972 11/86 110.142 4/87 107.813 other indirect supplies 24.908 sum. 1,081.236 (as per Dec. 31, 1987) l
Y 8-26) Amount of fuel of U.S.. origin previously consumed during 92fCa}jgg,g{,tgag}gt,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,, 163 kg U.235; reactor only in operation since end 1985. i Up to Dec. 31, 1987: total 205,000 mwd 27) Status of cooperation between reactor operator and Argonne Na}}ggal,(abgta}gry,jg,tgggggg,ggtighggg},gtggtag,{BEBI31, No cooperation. Cooperation between Nukem and RERTR in the field of MTR. 28) status of agreement between reactor operator and ANL to [fdVS2.90C19DT!01..................................... No agreement 29) Status of cooperation between reactor operator and IAEA [gguggg,ggtjgbggg3,gtggtag,,,,,,,,,,,,,,,,,,,,,,,,,,,,, No cooperation. l l l l l l l}}