Foreign Research Reactor Spent Nuclear Fuel -Reduced Enrichment Research and Test Reactors

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Reduced Enrichment for Research and Test Reactors
Nuclear Engineering Division at Argonne

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Foreign Research Reactor Spent Nuclear Fuel

Final Environmental Impact Statement Summary, Record of Decision, Federal Register Notices, and Related Documents:

Summary of Final Environmental Impact Statement on a Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel DOE/EIS-0218F, February 1996
Foreign Research Reactors that are Included in the Final Environmental Impact Statement DOE/EIS-0218F February 1996
Record of Decision (ROD) for the Final Environmental Impact Statement on a Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel The effective date of this Record of Decision is May 13, 1996.
Federal Register Notice on Establishment of the Fee Policy for Acceptance of Foreign Research Reactor Spent Nuclear Fuel Federal Register / Vol. 61, No. 103 / Tuesday May 28, 1996 / Notices, page 26507
Federal Register Notice on a Revision to the Record of Decision Federal Register / Vol. 61, No. 144 / Thursday, July 25, 1996 / Notices, page 38720.
The Department of Energy is revising the Record of Decision issued on May 13, 1996 (61 FR 25092), to allow the United States to take title to spent nuclear fuel and target material from foreign research reactors located in countries with other-than-high-income economies, as defined in the Final EIS (DOE/EIS-218F, February 1996), at locations other than the port of entry into the United States.

Documents intended to assist foreign research reactor operators in preparing to ship spent nuclear fuel:

Checklist for Foreign Research Reactor Site Assessments to Address Capability and Readiness to Ship Spent Nuclear Fuel
Guidelines Document on Preparatory Work Prior to Return of Spent Fuel of US-Origin from Foreign Research Reactors IAEA-TECDOC-..., DRAFT June 1996
Photon Dose Rates from Spent Fuel Assemblies with Relation to Self-Protection (Rev. 1) ANL/RERTR/TM-25, R. B. Pond and J.E. Matos, RERTR Program, Argonne National Laboratory, Argonne, Illinois, February 1996
Nuclear Mass Inventory, Photon Dose Rate, and Thermal Decay Heat of Spent Research Reactor Fuel Assemblies (Rev. 1) ANL/RERTR/TM-26, R. B. Pond and J.E. Matos, RERTR Program, Argonne National Laboratory, Argonne, Illinois, December 1996

2007 International RERTR Meeting

2008 International RERTR Meeting (RERTR-2008):
The Final Technical Program of the 30^th International RERTR Meeting is now available.
For more information visit RERTR-2008.

Useful Links

FUEL DEVELOPMENT
Low enriched uranium fuels for research and test reactors
REACTOR CONVERSION ANALYSES
Design and safety analyses for research and test reactors
MO-99 PRODUCTION
Radioisotope production

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Last modified on July 29, 2008 16:19 +0200