Occupational radiation dose assessment for the DOE spent-fuel storage facility
- Duke Engineering and Services, Charlotte, NC (United States)
- Duke Engineering & Services, Vienna, VA (United States)
To expedite the licensing process of the centralized interim storage facility (CISF), the U.S. Department of Energy has completed a CISF topical safety analysis report (TSAR). The TSAR will be used in licensing the CISF when a site is designated. An occupational radiation dose assessment of the facility operations is performed as part of the CISF design. The first phase of the CISF has the capability to receive, transfer, and store spent nuclear fuel (SNF) in dual-purpose casks. Currently, there are five vendor technologies under consideration. The preliminary dose assessment is based on estimated occupational exposures using traditional power plant independent spent-fuel storage installation (ISFSI) and transport cask-handling processes. The second step in the process is to recommend as-low-as-reasonably-achievable (ALARA) techniques to reduce potential exposures. A final dose assessment is completed implementing the ALARA techniques, and a review is performed to ensure that the design is in compliance with regulatory criteria. The dose assessment and ALARA evaluation are determined using the following input information: dose estimates from vendor safety analysis reports, ISFSI experience with similar systems, traditional methods of operations, expected CISF cask receipt rates, and feasible ALARA techniques.
- OSTI ID:
- 552563
- Report Number(s):
- CONF-971125-; ISSN 0003-018X; TRN: 98:001764
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 77; Conference: 1997 American Nuclear Society (ANS) winter meeting, Albuquerque, NM (United States), 16-20 Nov 1997; Other Information: PBD: 1997
- Country of Publication:
- United States
- Language:
- English
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