Criticality Safety Evaluation Report for the Multi-Canister Overpack
- Fluor Daniel Hanford, Inc., Richland, WA (United States); FDNW
This criticality safety evaluation report (CSER) addresses the criticality analysis for spent nuclear fuel (SNF) inside a multi-canister overpack (MCO). The results reported in this revision of the CSER have been upgraded to incorporate the basket designs from HNF-S-0426, Performance Specification for Spent Nuclear Fuel Multi-Canister Overpack (Goldmann 1998).
- Research Organization:
- Fluor Daniel Hanford, Inc., Richland, WA (United States)
- Sponsoring Organization:
- USDOE Office of Environmental Management (EM); USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC06-96RL13200
- OSTI ID:
- 798146
- Report Number(s):
- HNF--SD-SNF-CSER-005-Rev.5; ECN-647522
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
CONTAINERS
COPPER
CRITICALITY
Canister Storage Building
Cold Vacuum Drying Facility
Criticality Safety Evaluation Report
DRYING
EVALUATION
FUEL ASSEMBLIES
Monte Carlo N-Particle Transport Code
Multi-Canister Overpack
N-REACTOR
NUCLEAR FUELS
Nuclear Criticality Safety Program (NCSP)
SAFETY
STORAGE
STORAGE FACILITIES
Single Pass Reactor
Spent Nuclear Fuel
CONTAINERS
COPPER
CRITICALITY
Canister Storage Building
Cold Vacuum Drying Facility
Criticality Safety Evaluation Report
DRYING
EVALUATION
FUEL ASSEMBLIES
Monte Carlo N-Particle Transport Code
Multi-Canister Overpack
N-REACTOR
NUCLEAR FUELS
Nuclear Criticality Safety Program (NCSP)
SAFETY
STORAGE
STORAGE FACILITIES
Single Pass Reactor
Spent Nuclear Fuel