Published September 1999 | Version v1
Book

Plutonium management and multi-recycling in LWRs using an enriched uranium support

  • 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)

Optional Information

Notes
3 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)