Calculational framework for safety analyses of non-reactor nuclear facilities

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A calculational framework for the consequences analysis of non-reactor nuclear facilities is presented. The analysis framework starts with accident scenarios which are developed through a traditional hazard analysis and continues with a probabilistic framework for the consequences analysis. The framework encourages the use of response continua derived from engineering judgment and traditional deterministic engineering analyses. The general approach consists of dividing the overall problem into a series of interrelated analysis cells and then devising Markov chain like probability transition matrices for each of the cells. An advantage of this division of the problem is that intermediate output (as probability state ... continued below

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116 p.

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Coleman, J.R. June 1, 1994.

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Description

A calculational framework for the consequences analysis of non-reactor nuclear facilities is presented. The analysis framework starts with accident scenarios which are developed through a traditional hazard analysis and continues with a probabilistic framework for the consequences analysis. The framework encourages the use of response continua derived from engineering judgment and traditional deterministic engineering analyses. The general approach consists of dividing the overall problem into a series of interrelated analysis cells and then devising Markov chain like probability transition matrices for each of the cells. An advantage of this division of the problem is that intermediate output (as probability state vectors) are generated at each calculational interface. The series of analyses when combined yield risk analysis output. The analysis approach is illustrated through application to two non-reactor nuclear analyses: the Ulysses Space Mission, and a hydrogen burn in the Hanford waste storage tanks.

Physical Description

116 p.

Notes

INIS; OSTI as DE98005299

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  • Other Information: PBD: 1 Jun 1994

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  • Other: DE98005299
  • Report No.: LA-SUB--95-126
  • Grant Number: W-7405-ENG-36
  • DOI: 10.2172/654348 | External Link
  • Office of Scientific & Technical Information Report Number: 654348
  • Archival Resource Key: ark:/67531/metadc711132

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Office of Scientific & Technical Information Technical Reports

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Creation Date

  • June 1, 1994

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • June 14, 2016, 8:28 p.m.

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Coleman, J.R. Calculational framework for safety analyses of non-reactor nuclear facilities, report, June 1, 1994; New Mexico. (digital.library.unt.edu/ark:/67531/metadc711132/: accessed June 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.