SciTech Connect

Title: INERT-MATRIX FUEL: ACTINIDE ''BURINGIN'' AND DIRECT DISPOSAL

INERT-MATRIX FUEL: ACTINIDE ''BURINGIN'' AND DIRECT DISPOSAL Excess actinides result from the dismantlement of nuclear weapons (Pu) and the reprocessing of commercial spent nuclear fuel (mainly 241 Am, 244 Cm and 237 Np). In Europe, Canada and Japan studies have determined much improved efficiencies for burnup of actinides using inert-matrix fuels. This innovative approach also considers the properties of the inert-matrix fuel as a nuclear waste form for direct disposal after one-cycle of burn-up. Direct disposal can considerably reduce cost, processing requirements, and radiation exposure to workers.
Authors: ;
Publication Date:
OSTI Identifier:805759
Report Number(s):DOE/ID/13767
TRN: US0300997
DOE Contract Number:FG07-99ID13767
Resource Type:Technical Report
Data Type:
Resource Relation:Other Information: PBD: 30 Oct 2002
Research Org:University of Michigan (US)
Sponsoring Org:(US)
Country of Publication:United States
Language:English
Subject: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 45 MILITARY TECHNOLOGY, WEAPONRY, AND NATIONAL DEFENSE; ACTINIDES; BURNUP; CANADA; EUROPE; JAPAN; NUCLEAR FUELS; NUCLEAR WEAPONS; RADIATIONS; RADIOACTIVE WASTES; REPROCESSING