Intact and Degraded Criticality Calculations for the Codisposal of Shippingport LWBR Spent Nuclear Fuel in a Waste Package
- Yucca Mountain Project, Las Vegas, NV (United States)
The objective of this calculation is to characterize the nuclear criticality safety concerns associated with the codisposal of the U.S. Department of Energy's (DOE) Shippingport Light Water Breeder Reactor (SP LWBR) Spent Nuclear Fuel (SNF) in a 5-Defense High-Level Waste (5-DHLW) Waste Package (WP), which is to be placed in a Monitored Geologic Repository (MGR). The scope of this calculation is limited to the determination of the effective neutron multiplication factor (keff) for intact- and degraded-mode internal configurations of the codisposal WP containing Shippingport LWBR seed-type assemblies. The results of this calculation will be used to evaluate criticality issues and support the analysis that is planed to be performed to demonstrate the viability of the codisposal concept for the MGR. This calculation is associated with the waste package design and was performed in accordance with the DOE SNF Analysis Plan for FY 2000. The document has been prepared in accordance with the Administrative Procedure AP-3.12Q, Calculations.
- Research Organization:
- Yucca Mountain Project, Las Vegas, NV (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 893822
- Report Number(s):
- CAL-EDC-NU-000004-Rev-00; MOL.20000922.0093, DC# 25561; TRN: US0606132
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ADMINISTRATIVE PROCEDURES
BREEDER REACTORS
CRITICALITY
DESIGN
MULTIPLICATION FACTORS
NEUTRONS
NUCLEAR FUELS
SAFETY
VIABILITY
WASTES
WATER
SPENT FUELS
Nuclear Criticality Safety Program (NCSP)
Criticality
Breeder Reactors
Neutrons
Nuclear Fuels
Waste Disposal
Shippingport Light Water Breeder Reactor
SP LWBR
Spent Nuclear Fuel
SNF