Addressing the Axial Burnup Distribution in PWR Burnup Credit Criticality Safety
Description
This paper summarizes efforts related to developing a technically justifiable approach for addressing the axial burnup distribution in PWR burnup-credit criticality safety analyses. The paper reviews available data on the axial variation in burnup and the effect of axial burnup profiles on reactivity in a SNF cask. A publicly available database of profiles is examined to identify profiles that maximize the neutron multiplication factor, keff, assess its adequacy for general PWR burnup credit analyses, and investigate the existence of trends with fuel type and/or reactor operations. For this assessment, a statistical evaluation of the keff values associated with the profiles in the axial burnup profile database was performed that identifies the most reactive profiles as statistical outliers that are not representative of typical discharged SNF assemblies. The impact of these bounding profiles on the neutron multiplication factor for a high-density burnup credit cask is quantified. Finally, analyses are presented to quantify the potential reactivity consequence of assemblies with axial profiles that are not bounded by the existing database. The paper concludes with findings for addressing the axial burnup distribution in burnup credit analyses
Availability note (English)
Available from PURL: https://www.osti.gov/servlets/purl/788633-H6nqbg/native/Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- P--01-111370
Conference
- Title
- 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety
- Dates
- 2001
- Place
- United States (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 33006136
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; CRITICALITY; MULTIPLICATION FACTORS; NEUTRONS; PWR TYPE REACTORS; REACTOR OPERATION; SAFETY ANALYSIS; SPENT FUELS
- Descriptors DEC
- BARYONS; ELEMENTARY PARTICLES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FERMIONS; FUELS; HADRONS; MATERIALS; NUCLEAR FUELS; NUCLEONS; OPERATION; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- AC05-00OR22725
- Funding organization
- Nuclear Regulatory Commission (United States)