Investigation of Burnup Credit Issues in BWR Fuel
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Computational Physics and Engineering Division; ORNL
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Computational Physics and Engineering Division
Calculations for long-term-disposal criticality safety of spent nuclear fuel requires the application of burnup credit because of the large mass of fissile material that will be present in the repository. Burnup credit calculations are based on depletion calculations that provide a conservative estimate of spent fuel contents, followed by criticality calculations to assess the value of keff for a spent fuel cask or a fuel configuration under a variety of probabilistically derived events. In order to ensure that the depletion calculation is conservative, it is necessary to both qualify and quantify assumptions that can be made in depletion models used to characterize spent fuel. Most effort in the United States this decade has focused on burnup issues related to pressurized-water reactors. However, requirements for the permanent disposal of fuel from boiling-water reactors has necessitated development of methods for prediction of spent fuel contents for such fuels. Concomitant with such analyses, validation is also necessary. This paper provides a summary of initial efforts at the Oak Ridge National Laboratory to better understand and validate spent fuel analyses for boiling-water-reactor fuel.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Computational Physics and Engineering Division
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC05-96OR22464
- OSTI ID:
- 7629
- Report Number(s):
- ORNL/CP-103312; 64 70 61 80 1; ON: DE00007629
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
Assembly ZZ Data
Axial Burnup Model
BWR Type Reactors
Boiling-Water-Reactor (BWR) Fuel
Burnup
Fissile Material
Fuel Configuration
HELIOS
KENO-V.a
Nuclear Criticality Safety Program (NCSP)
SAS2H
Spent Fuel Cask
Spent Fuel Elements
Spent Nuclear Fuel
Spent Pressurized-Water-Reactor (PWR) Fuel