Bayesian risk-based acceptance criteria

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Mechanistic (or deterministic) analysis is traditionally performed in the process of designing a new nuclear reactor or reactor core and also as part of the safety analysis of existing reactors or reload cores. Mechanistic accident analysis is characterized by the specification of an initial operating condition, an initiating event, and subsequent system faults. These subsequent faults are often chosen, through such mechanisms as the worst single failure criterion, so as to maximize the consequences of the accident. Thus, the behavior of all reactor system hardware is prescribed before this analysis begins. Mechanistic analysis then attempts to predict the dynamic response ... continued below

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26 p.

Creation Information

Martz, H.F.; Abramson, L.R. & Johnson, J.W. April 1, 1996.

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Description

Mechanistic (or deterministic) analysis is traditionally performed in the process of designing a new nuclear reactor or reactor core and also as part of the safety analysis of existing reactors or reload cores. Mechanistic accident analysis is characterized by the specification of an initial operating condition, an initiating event, and subsequent system faults. These subsequent faults are often chosen, through such mechanisms as the worst single failure criterion, so as to maximize the consequences of the accident. Thus, the behavior of all reactor system hardware is prescribed before this analysis begins. Mechanistic analysis then attempts to predict the dynamic response of the system and usually involves detailed reactor physics and thermal-hydraulic predictions of the system behavior, including such parameters as power distributions in the reactor core, coolant temperatures and flow rates, and fuel clad temperature distributions. The objective of this analysis has typically been to establish and verify reactor operating limits and technical specifications, so that severe core damage (SCD) is prevented for a wide variety of reactor accidents.

Physical Description

26 p.

Notes

INIS; OSTI as DE96010488

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  • International topical meeting on probabilistic safety assessment - moving toward risk based regulation, Park City, UT (United States), 29 Sep - 3 Oct 1996

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  • Other: DE96010488
  • Report No.: LA-UR--96-1422
  • Report No.: CONF-960912--22
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 286163
  • Archival Resource Key: ark:/67531/metadc664418

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  • April 1, 1996

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  • June 29, 2015, 9:42 p.m.

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  • July 28, 2016, 7:06 p.m.

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Martz, H.F.; Abramson, L.R. & Johnson, J.W. Bayesian risk-based acceptance criteria, article, April 1, 1996; New Mexico. (digital.library.unt.edu/ark:/67531/metadc664418/: accessed September 19, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.