Comparison of Computational Estimations of Reactivity Margin From Fission Products and Minor Actinides in PWR Burnup Credit
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); ORNL
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
This paper has presented the results of a computational benchmark and independent calculations to verify the benchmark calculations for the estimation of the additional reactivity margin available from fission products and minor actinides in a PWR burnup credit storage/transport environment. The calculations were based on a generic 32 PWR-assembly cask. The differences between the independent calculations and the benchmark lie within 1% for the uniform axial burnup distribution, which is acceptable. The Δk for KENO - MCNP results are generally lower than the other Δk values, due to the fact that HELIOS performed the depletion part of the calculation for both the KENO and MCNP results. The differences between the independent calculations and the benchmark for the non-uniform axial burnup distribution were within 1.1%.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USNRC
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 786339
- Report Number(s):
- P01--111352
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING
97 MATHEMATICS AND COMPUTING
ACTINIDES
BENCHMARKS
BURNUP
COMPUTER CALCULATIONS
CRITICALITY
FISSION PRODUCTS
KENO
MCNP
Nuclear Criticality Safety Program (NCSP)
PWR TYPE REACTORS
Results
SPENT FUEL CASKS
SPENT FUEL STORAGE
TRANSPORT
Verification