Application of Scale-4 Depletion/Criticality Sequences in Burnup Credit Analyses
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
The concept of allowing reactivity credit for the transmuted state of spent fuel complicates the criticality analysis by requiring the specification of the fuel mixture to potentially include large numbers of isotopes representative of the fuel conditions. These conditions include the initial enrichment, local or average burnup conditions depending on the analysis approach, and the post-shutdown cooling time. In the development of an analysis methodology to evaluate spent fuel shipping and transport casks (flasks) based on this burnup credit, commercial reactor critical configurations were evaluated as potential experimental spent fuel criticals. This paper describes how the SCALE-4 depletion sequences (SAS2H), the cross-section processing sequence (CSASN), and the criticality module (KENO V.a) were used to evaluate these reactor criticals. A description of a newly developed sequence for linking SAS2H calculated burnup-dependent isotopics to KENO V.a mixing tables [SAS2H Nuclide Inventories for KENO Runs (SNIKR)] is also included.
- 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)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10110343
- Report Number(s):
- CONF-9109217-5; ON: DE92005125
- Resource Relation:
- Conference: Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding and Heat Transfer Capabilities, Gif-sur-Yvette (France), 17-20 Sep 1991; Other Information: PBD: [1991]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
07 ISOTOPE AND RADIATION SOURCES
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
97 MATHEMATICS AND COMPUTING
SPENT FUEL STORAGE
PWR TYPE REACTORS
SPENT FUELS
CRITICALITY
X CODES
O CODES
S CODES
K CODES
BURNUP
CHEMICAL ANALYSIS
SAFETY
ACTINIDES
CROSS SECTIONS
REACTOR PHYSICS
Nuclear Criticality Safety Program (NCSP)
Criticality Analysis
Analysis Methodology
Fuel Mixture
Fuel Conditions
Spent Fuel Shipping and Transport Casks (Flasks) Evaluation
SCALE-4 Depletion Sequences (SAS2H)
Cross-Section Processing Sequence (CSASN)
Criticality Module (KENO V.a)
SAS2H Nuclide Inventories for KENO Runs (SNIKR)
050900
054000
210200
990200
TRANSPORT, HANDLING, AND STORAGE
HEALTH AND SAFETY
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
MATHEMATICS AND COMPUTERS