Optimization and implementation study of plutonium disposition using existing CANDU Reactors. Final report

Technical Report · Sun Sep 01 04:00:00 EDT 1996

DOI:https://doi.org/10.2172/373927· OSTI ID:373927

Since early 1994, the Department of Energy has been sponsoring studies aimed at evaluating the merits of disposing of surplus US weapons plutonium as Mixed Oxide (MOX) fuel in existing commercial Canadian Pressurized Heavy Water reactors, known as CANDU`s. The first report, submitted to DOE in July, 1994 (the 1994 Executive Summary is attached), identified practical and safe options for the consumption of 50 to 100 tons of plutonium in 25 years in some of the existing CANDU reactors operating the Bruce A generating station, on Lake Huron, about 300 km north east of Detroit. By designing the fuel and nuclear performance to operate within existing experience and operating/performance envelope, and by utilizing existing fuel fabrication and transportation facilities and methods, a low cost, low risk method for long term plutonium disposition was developed. In December, 1995, in response to evolving Mission Requirements, the DOE requested a further study of the CANDU option with emphasis on more rapid disposition of the plutonium, and retaining the early start and low risk features of the earlier work. This report is the result of that additional work.

• Research Organization: AECL Technologies, Inc., Rockville, MD (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC03-94SF20218
• OSTI ID: 373927
• Report Number(s): DOE/SF/20218--T3; ON: DE96014914
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CANDU TYPE REACTORS
COST ESTIMATION
DATA
DESIGN
FEASIBILITY STUDIES
FUEL FABRICATION PLANTS
MIXED OXIDE FUELS
NUCLEAR FUELS
NUCLEAR MATERIALS MANAGEMENT
NUCLEAR WEAPONS DISMANTLEMENT
PLUTONIUM
PROGRESS REPORT
REACTOR CORES
REACTOR OPERATION