Published September 1999
| Version v1
Book
Plutonium management and multi-recycling in LWRs using an enriched uranium support
Creators
- 1. CEA DRN/DER/SPRC, 13108 St-Paul-lez-Durance (France)
- 2. Cogema BCR/DSDP/DSD, 78182 St-Quentin en Yvelines (France)
- 3. CEA DRN/DMT/SERMA, 91191 Gif-sur-Yvette cedex (France)
Description
The MIX concept proposes a realistic trade-off between the will to utilize Pu in actual PWRs, and the necessity (for economic reasons) to go toward long cycle lengths and high burnups. Indeed, if burnups around 50 GWd/t have to be reached with MOX, then the Pu content must be around 10% which impairs the control mean efficiency. In the MIX, the Pu content is limited at 4% and the uranium is enriched in order to attain the target burnups; even with a poor quality Pu, the necessary U235 enrichment is lower than for the UOX core. The core characteristics are presented, as well as the transition from a UOX core to a MIX core, and two accidental configurations (cooling transient and control cluster ejection)
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
- 53059261
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; COOLING; EFFICIENCY; ENRICHED URANIUM; ISOTOPE SEPARATION; NUCLEAR MATERIALS MANAGEMENT; PLUTONIUM; PWR TYPE REACTORS; RADIOACTIVE WASTE MANAGEMENT; RECYCLING; TRANSIENTS; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; ELEMENTS; ENRICHED URANIUM REACTORS; EVEN-ODD NUCLEI; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPE ENRICHED MATERIALS; ISOTOPES; MANAGEMENT; MATERIALS; METALS; MINUTES LIVING RADIOISOTOPES; NUCLEI; POWER REACTORS; RADIOISOTOPES; REACTORS; SEPARATION PROCESSES; SPONTANEOUS FISSION RADIOISOTOPES; THERMAL REACTORS; TRANSURANIUM ELEMENTS; URANIUM; URANIUM ISOTOPES; WASTE MANAGEMENT; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 3 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)