EPRI performed a Probabilistic Risk Assessment (PRA) of a dry spent fuel storage cask. The study was performed for a bolted cask at a “generic” pressurized water reactor site. A generic site was chosen so the widest variety of challenges could be considered. The study calculates the annual individual radiological risk and consequences associated with a single cask life cycle, where the life cycle is divided into three phases: loading, on-site transfer, and on-site storage. The project used standard methods of PRA with the following analysis tasks: initiating event (IE), data, human reliability, structural, thermal hydraulic, accident sequence, and consequence. The results shows that the risk is extremely low with no calculated early fatalities and a first year risk of latent cancer fatality of 3.5E−11 per year per cask. Subsequent year risk to the general public is even lower; with, again, no early fatalities and a cancer risk of 4.2E−12.
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12th International Conference on Nuclear Engineering
April 25–29, 2004
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4689-X
PROCEEDINGS PAPER
Probabilistic Risk Assessment of Bolted Dry Spent Fuel Storage Cask
Jeffrey T. Mitman,
Jeffrey T. Mitman
Electric Power Research Institute, Palo Alto, CA
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Ken Canavan
Ken Canavan
Electric Power Research Institute, Columbia, NJ
Search for other works by this author on:
Jeffrey T. Mitman
Electric Power Research Institute, Palo Alto, CA
Ken Canavan
Electric Power Research Institute, Columbia, NJ
Paper No:
ICONE12-49607, pp. 273-281; 9 pages
Published Online:
November 17, 2008
Citation
Mitman, JT, & Canavan, K. "Probabilistic Risk Assessment of Bolted Dry Spent Fuel Storage Cask." Proceedings of the 12th International Conference on Nuclear Engineering. 12th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 25–29, 2004. pp. 273-281. ASME. https://doi.org/10.1115/ICONE12-49607
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