Transportation Implications of a Closed Fuel Cycle.
- University of Nevada, Reno, NV (United States)
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Transportation for each step of a closed fuel cycle is analyzed in consideration of the availability of appropriate transportation infrastructure. The United States has both experience and certified casks for transportation that may be required by this cycle, except for the transport of fresh and used MOX fuel and fresh and used Advanced Burner Reactor (ABR) fuel. Packaging that had been used for other fuel with somewhat similar characteristics may be appropriate for these fuels but would be inefficient. Therefore, the required neutron and gamma shielding, heat dissipation, and criticality were calculated for MOX and ABR fresh and spent fuel. Criticality would not be an issue, but the packaging design would need to balance neutron shielding and regulatory heat dissipation requirements.
- Research Organization:
- Sandia National Lab. (SNL-CA), Livermore, CA (United States); Univ. of Nevada, Reno, NV (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 1027066
- Report Number(s):
- SAND2010-6791C; TRN: US1105165
- Resource Relation:
- Conference: PATRAM 2010, London (United Kingdom), 3-8 Oct 2010
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
CASKS
CRITICALITY
DESIGN
FUEL CYCLE
PACKAGING
SHIELDING
SPENT FUELS
TRANSPORT
Nuclear Criticality Safety Program (NCSP)
Closed Fuel Cycle
Analyzing
Transportation
MOX Fuel and Fresh
Burner Reactor (ABR) Fuel
Packaging
Neutron and Gamma Shielding
Heat Dissipation
and Criticality