Recycle transmutation to reduce minor actinide for geologic disposal by using high flux LWR
Creators
- 1. Research Laboratory for Nuclear Reactor, Tokyo Institute of Technology, 2-12-1 O-okayama, Meguro-ku, Tokyo 152-8550 (Japan)
Description
Geologic disposal scenario combined with P and T (partitioning and transmutation) treatment has an inherent merit to avoid the unanticipated uncertainty which might take place in a super-long period existing in geologic disposal. A part of this study has a significant role to realize the P and T treatment of MA (minor actinides) and LLFP (long-lived fission products). P and T treatment is possible to make short the period of isolation and realize the zero-release GSC (glass-solidified canister), therefore an unanticipated uncertainty might take place in a super-long period in geologic disposal may be able to be avoided. If P and T treatment can make the requirement for isolation of GSC shorter than 1,000 years, it may be no need to verify the performance of scenario, which will be obtained by the field test for a super-long period. Advanced performance of BTR (burning and/or transmutation reactor) based on 3.3 GWt-HFBWR (high flux BWR) was evaluated to understand the optimum recycle BIT treatment of MA included in the discharged fuel from the current LWR. The separation method in transmutation loop was assumed to be done only by chemical separation, and not by isotope separation. Thus, R and P (reprocessing and partitioning) process can recover MA and separate LLFP as the chemical component level. So, the mass or component, which go out from R and P transmutation loop is only SLFP (short-lived fission product), which was produced by fission reaction
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- Jackson Hole, Wyoming (United States)
- Imprint Pagination
- 8 p.
Conference
- Title
- International Conference on Future Nuclear Systems - Nuclear Technology - Bridging the Millennia
- Acronym
- Global'99
- Dates
- 29 Aug - 3 Sep 1999
- Place
- Las Vegas, NV (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 53059340
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTINIDES; BWR TYPE REACTORS; FIELD TESTS; FISSION; FISSION PRODUCTS; GLASS; ISOTOPE SEPARATION; NUCLEAR FUELS; PARTITION; PERFORMANCE; REPROCESSING; TRANSMUTATION
- Descriptors DEC
- ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; ISOTOPES; MATERIALS; METALS; NUCLEAR REACTIONS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)