Shielding analysis considerations for spent-fuel transport and storage casks
- Nuclear Assurance Corporation, Norcross, GA (USA)
Spent-fuel transport and storage casks are expected to be major components of the solution to the problem of spent-fuel disposal in the United States. In keeping with as low as reasonably achievable dose levels, these casks are designed to incorporate shielding for neutrons and gamma rays to minimize the radiation exposure associated with spent-fuel cask storage, transport, and maintenance. Nuclear Assurance Corporation (NAC) has obtained good results from the QAD-CG computer code for essentially monoenergetic {sup 60}Co gamma-ray calculations. The QAD-CG code is also used in the evaluation of the dose rate contribution from the active fuel region. The energy distribution of the neutrons and gamma rays emitted in the fuel region must also be taken into account. The dose rate contribution from the fuel region is both spatially and energy dependent. The NAC method of determining the dose rate contribution assumes that the energy dependence and the spatial dependence can be treated separately. An XSDRNPM analysis is performed to take into account the energy dependence. As the technology associated with cask designs improves, the shielding analyses required to obtain accurate dose rates will become more complex.
- OSTI ID:
- 5477552
- Report Number(s):
- CONF-891103--
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 60; ISSN TANSA; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
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420204* -- Engineering-- Shipping Containers
ACCURACY
ALARA
CALCULATION METHODS
CASKS
COMPUTER CODES
CONTAINERS
DESIGN
DEVELOPED COUNTRIES
DOSES
ECONOMICS
ELECTROMAGNETIC RADIATION
ENERGY TRANSFER
GAMMA RADIATION
HEAT TRANSFER
HIGH-LEVEL RADIOACTIVE WASTES
IONIZING RADIATIONS
MAINTENANCE
MATERIALS
MATHEMATICAL MODELS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NORTH AMERICA
OPTIMIZATION
Q CODES
RADIATION DOSES
RADIATION PROTECTION
RADIATION TRANSPORT
RADIATIONS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REGULATIONS
SHIELDING
SPENT FUEL CASKS
SPENT FUEL STORAGE
STORAGE
TRANSPORT
USA
WASTES