Analysis of Burnup Credit in Fuel Storage with CASMO
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:6942644
Recent trends in nuclear power plant operation have tended toward longer cycles with reload fuel of high (> 3.5 wt% 235U) enrichments. At the same time, the need for greater spent-fuel pool capacity has reduced storage canister spacing to the point where maximum allowable fresh enrichments are lower than those necessary for longer cycles. As a result, burnup credit analysis has been applied to spent-fuel storage rack criticality analysis. This allows the placement, after exposure, of higher fuel enrichments in the spent-fuel racks than would normally be allowed under the assumption of a fresh condition. The CASMO lattice physics code is used to analyze burnup credit on the Maine Yankee spent-fuel storage racks. Unit cell sensitivity analysis of rack criticality to in-core depletion effects and to out-of-core decay is considered. Also, large array criticality analysis is performed to study options for the placement of fresh and burned assemblies.
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 6942644
- Report Number(s):
- CONF-8711195-
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society Journal Volume: 55
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
97 MATHEMATICS AND COMPUTING
ACTINIDES
BURNUP
C CODES
CASMO
COMPUTER CODES
CRITICALITY
ELEMENTS
ENRICHED URANIUM
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
FUEL MANAGEMENT
Fresh and Burned Assemblies Placement
ISOTOPE ENRICHED MATERIALS
Large Array Criticality Analysis
MAINE YANKEE REACTOR
MATERIALS
METALS
Nuclear Criticality Safety Program (NCSP)
POWER REACTORS
PWR TYPE REACTORS
REACTIVITY
REACTOR COMPONENTS
REACTORS
SAFETY
SENSITIVITY ANALYSIS
SPENT FUEL ELEMENTS
SPENT FUEL STORAGE
STORAGE
THERMAL REACTORS
URANIUM
WATER COOLED REACTORS
WATER MODERATED REACTORS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
97 MATHEMATICS AND COMPUTING
ACTINIDES
BURNUP
C CODES
CASMO
COMPUTER CODES
CRITICALITY
ELEMENTS
ENRICHED URANIUM
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
FUEL MANAGEMENT
Fresh and Burned Assemblies Placement
ISOTOPE ENRICHED MATERIALS
Large Array Criticality Analysis
MAINE YANKEE REACTOR
MATERIALS
METALS
Nuclear Criticality Safety Program (NCSP)
POWER REACTORS
PWR TYPE REACTORS
REACTIVITY
REACTOR COMPONENTS
REACTORS
SAFETY
SENSITIVITY ANALYSIS
SPENT FUEL ELEMENTS
SPENT FUEL STORAGE
STORAGE
THERMAL REACTORS
URANIUM
WATER COOLED REACTORS
WATER MODERATED REACTORS