Advanced accident sequence precursor analysis level 2 models [electronic resource].
- Washington, D.C. : U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, 1996.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- pages 409-431 : digital, PDF file
- Additional Creators:
- U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- The U.S. Nuclear Regulatory Commission Accident Sequence Precursor program pursues the ultimate objective of performing risk significant evaluations on operational events (precursors) occurring in commercial nuclear power plants. To achieve this objective, the Office of Nuclear Regulatory Research is supporting the development of simple probabilistic risk assessment models for all commercial nuclear power plants (NPP) in the U.S. Presently, only simple Level 1 plant models have been developed which estimate core damage frequencies. In order to provide a true risk perspective, the consequences associated with postulated core damage accidents also need to be considered. With the objective of performing risk evaluations in an integrated and consistent manner, a linked event tree approach which propagates the front end results to back end was developed. This approach utilizes simple plant models that analyze the response of the NPP containment structure in the context of a core damage accident, estimate the magnitude and timing of a radioactive release to the environment, and calculate the consequences for a given release. Detailed models and results from previous studies, such as the NUREG-1150 study, are used to quantify these simple models. These simple models are then linked to the existing Level 1 models, and are evaluated using the SAPHIRE code. To demonstrate the approach, prototypic models have been developed for a boiling water reactor, Peach Bottom, and a pressurized water reactor, Zion.
- Report Numbers:
- E 1.99:nureg/cp--0149-vol.2
E 1.99: conf-9510156--vol.2
- Other Subject(s):
- Published through SciTech Connect.
23. water reactor safety information meeting, Bethesda, MD (United States), 23-25 Oct 1995.
Rempe, J.L.; Brownson, D.A.; Galyean, W.J.
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