Burnup credit implementation in spent fuel management
Creators
- 1. CEA Cadarache, Dept. d'Etudes des Reacteurs (DER-SPRC/LEPh), 13 - Saint-Paul-lez-Durance (France)
Description
The criticality safety analysis of spent fuel management systems has traditionally assumed that the fuel is fresh. This results in significant conservatism in the calculated value of the system's reactivity. The concept of allowing reactivity credit for spent fuel offers economic incentives. Burnup Credit (BUC) could reduce mass limitation during dissolution of highly enriched PWR assemblies at the La Hague reprocessing plant. Furthermore, accounting for burnup credit enables the operator to avoid the use of Gd soluble poison in the dissolver for MOX assemblies. Analyses performed by DOE and its contractors have indicated that using BUC to maximize spent fuel transportation cask capacities is a justifiable concept that would result in public risk benefits and cost savings while fully maintaining criticality safety margins. In order to allow for Fission Products and Actinides in Criticality-Safety analyses, an extensive BUC experimental programme has been developed in France in the framework of the CEA-COGEMA collaboration. The use of burnup credit implies a verification of the fuel burnup before loading for transport, storage, disposal, or reprocessing each assembly, to make sure that the burnup level achieved complies with the criteria established. Independent measurement systems, e.g. gamma spectrum detection systems, are needed to perform a true independent measurement of assembly burnup, without reliance on reactor records, using the gamma emission signatures fission products (mainly Cesium isotopes). (author)
Additional details
Publishing Information
- Imprint Title
- Modern reactor physics and the modelling of complex systems
- Imprint Pagination
- 430 p.
- Journal Page Range
- p. 356-371
- Report number
- INIS-FR--249
Conference
- Title
- The 1998 Frederic Joliot summer school in reactor physics
- Dates
- 17-26 Aug 1998
- Place
- Cadarache (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 32007985
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BOUNDARY CONDITIONS; BURNUP; CRITICALITY; NUCLEAR MATERIALS MANAGEMENT; REPROCESSING; SAFETY; SPENT FUELS
- Descriptors DEC
- ENERGY SOURCES; FUELS; MANAGEMENT; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; SEPARATION PROCESSES
Optional Information
- Notes
- 22 refs.