ML20154H349
| ML20154H349 | |
| Person / Time | |
|---|---|
| Issue date: | 01/21/1986 |
| From: | Grimsley D NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Aftergood S COMMITTEE TO BRIDGE THE GAP |
| Shared Package | |
| ML20154H353 | List: |
| References | |
| FOIA-85-745 NUDOCS 8603100260 | |
| Download: ML20154H349 (3) | |
Text
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, UNITED STATES !
, g NUCLEAR REGULATORY COMMISSION s j WASHINGTON. D. C. 20655
~s...../ :
JAN 2 i W Mr. Steven Aftergood Committee to Bridge the Gap 1637 Butler Avenue #203 IN RESPONSE REFER Los Angeles, CA 90025 TO F01A-85-745
Dear Mr. Aftergood:
This is in response to your letter dated November 4, 1985, in which you requested, pursuant to the Freedom of Information Act, copies of all papers delivered at the International Meeting on Reduced Enrichment for Research and Test Reactors held October 14-16, 1985, in Petten, The Netherlands.
The documents located on the enclosed appendix are enclosed and are already being placed in the NRC's Public Document Room (PDR).
Sincerely,
&Y Donnie H. Grimsley, Director Division of Rules and Records Office of Administration
Enclosures:
As stated 8603100260 860121 PDR FDIA AFTERGO95-745 PDR 1
Re: F01A-85-745 APPENDIX
- 1. Final Results of Qualification Testing of TRIGA Fuel in the Oak Ridge Research Reactor Including Post-Irradiation Examination by Robert H.
Chestworth and Gordon B. West. (21 pages)
- 2. Refueling the RPI Reactor Facility with Low-Enrichment Fuel by D. R. Harris et. al. (6 pages)
- 3. Status of LEU Programs at Babcock & Wilcox - Ken Bagacik Research and Test Reactor Fuel Element Facility. (9 pages)
' 4. Licensing Considerations in Converting NRC-Licensed Non-Power Reactors from High-Enriched to Low-Enriched Uranium Fuels by Robert E. Carter. (8 pgs)
- 5. Programme (48 pages) _
- 6. Present Status of Reduced Enrichment Program for Research and Test Reactor Fuels in Japan by Ichiro Miyanaga and Kazuo Kamei. (12 pages)
- 7. Reduced Enrichment Activities at GKSS by W. Krull dated October 14-16, 1985. (10 pages)
- 8. Rapport D'Avancement Sur La Reduction De L'Enrichissement Du Combustible Dans Les Reacteurs Experimentaux Du Cea. (9 pages)
- 9. Irradiation Performance of Reduced-Enrichment Fuels Tested Under the U.S. Pertr Program by J. L. Snelgrove et. al. (10 pages)
- 10. Licensing Considerations in Converting NRC-Licensed Non-Power Reactors from High-Enriched to Low-Enriched Uranium Fuels by Robert E. Carter. (8 pages)
- 11. Core Management and Reactor Physics Aspects of the Conversion of the NRU Reactor to LEU by M. D. Atfield. (10 pages)
- 12. Progress Report on the Design of the Compact Core for Upgrading the Munich Research Reactor by K. Boning et. al. (9 pages)
- 13. A Comparison of the Radiological Consequences of a HEU and LEU Fueled Research Reactor by J. G. Kollas. (11 pages)
- 14. The Conversion of the Dido-Type Reactor FRJ-2 Studies and Conclusions by A. Stromich et. al. (10 pages)
- 15. Study on Temperature Coefficients of MEU and HEU Cores in the KUCA by Keiji Kanda et. al. (10 pages)
- 16. C.E.R.C.A. Romans - MTR Fuel at C.E.R.C.A. Status of Development -
October 1985 by Y. Fanjas. (19 pages)
)
Re: F01A-85-745 APPENDIX
- 17. Status of Development and Irradiation Performance of Advanced Proliferation Resistant MTR Fuel at NUKEM by M. Hrovat et. al. (9 pages)
- 18. The Fabrication and Performance of Canadian Silicide Dispersion Fuel for Test Reactors by D. F. Sears et. al. (15 pages)
- 19. MTRs - Experience with Modernisation and Upgrading by J. A. Collins-Smith. (8 pgs)
- 20. A Safety Analysis of the Research Reactor JRR-3 by Taikan Harami et al. (10 pgs)
- 21. Minimum Cladding Thickness of Material Test Reactor Fuel Plates by Jurgen Deckers. (10 pages)
~
- 22. Reduced-Reactivity-Swing LEU Fuel Cycle Analyses of HFR Petten by J. R. Deen and J. L. Snelgrove. (13 pages) ,
- 23. LEU Fuel Elements Manufacturing in Argentina by D. R. Giorsett'i et. al.- -
by October 14th/16th, 1985. (11 pages)
- 24. KUR Core Conversion - Neutronics Calculations by Keiji Kanda et. al. (10 pages)
- 25. LEU-Plate Irradiation at FRJ-2 (DIDO) Under the German AF-Programe by E. Gross et. al. (13 pages)
- 26. A Comparative and Predictive Study of the Annual Fuel Cycle Costs for HEU and LEU Fuels in the High Flux Reactor, Petten, 1985-1993 by R. L. Moss and P. May. (32 pages)
- 27. - Development of a 3-Dimensional Calculation Model of the Danish Research Reactor DR3 to Analyse a Proposal to a New Core Design Called Ring-Core by Erik Nonbol. (10 pages)
- 28. Critical Experiments of JMTRC MEU Cores (II) by S. Shimakawa et. al. (10 pages)
- 29. Development of Heat Transfer Package for Core Thermal-Hydraulic Design and Analysis of Upgraded JRR-3 by Yukio Sudo et. al. (10 pages)
- 30. Differential Thermal Analysis and Metallographic Examinations by Palle Toft and Arne Jensen. (9 pages)
- 31. Neutronic and Thermal-Hydraulic Calculations for the Conversion of the 5 MW "La Reina" Reactor Using MEU Fuel by J. Klein et. al. (.41 pages)
- 32. IAEA-SR-119/27 - The Cold Neutron Source for the FRG-1 Research Reactor at the GKSS Research Centre by W. Krull et. al. (27 pages)
- 33. Remarks by James K. Asselstine on Reduced Enrichment for Research and Test Reactors, Petten, The Netherlands - October 14, 1985, A Technical Solution to a Difficult Problem--An Update. (7 pages)