Evaluation of severe accident risks and the potential for risk reduction: Surry Power Station, Unit 1: Draft report for comment

Benjamin, A.S.; Boyd, G.J.; Kunsman, D.M.; Murfin, W.B.; Williams, D. C.

doi:10.2172/6658846

Cited by 6 publications

(3 citation statements)

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“…In the first iteration, the interface between source-term analysis and consequence analysis was accomplished by a clustering procedure in three dimensions (Ref. 38, Appendix C). This procedure used the k-means clustering algorithm(39) in conjunction with three measures of radiological potential.…”

Section: Discussionmentioning

confidence: 99%

“…The second number EF, is the mean number of early fatalities predicted by a full h4ACCS calculation for an 1-131 release of size EQi. A set of pairs of this form was generated for each NUREG-1150 plant using the same site-specific data (38) that was used in the final consequence calculations with MACCS for the integrated risk assessments. The MACCS calculations for the individual releases (i-e., the EQJ assumed an instantaneous ground-level release, no plume rise, and normal activity by the exposed population.…”

Section: =Dfck (K; Rfk I K ) Sfc Tc; =K; R F K I K Tc; (Dfck Sfck)mentioning

confidence: 99%

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A Methodology for Grouping Source Terms for Consequence Calculations in Probabilistic Risk Assessments

1990

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The individual plant analyses in the U.S. Nuclear Regulatory Commission's reassessment of the risk from commercial nuclear power plants (NUREG-1 150) consist of four parts: systems analysis, accident-progression analysis, source-term analysis, and consequence analysis. Careful definition of the interfaces between these parts is necessary for both information flow and computational efficiency. This paper describes the procedure used to define the interface between the sourceterm analysis and the consequence analysis. This interface is accomplished by forming groups of source terms with similar properties and then performing one set of MACCS calculations for each group.

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Section: Discussionmentioning

confidence: 99%

Section: =Dfck (K; Rfk I K ) Sfc Tc; =K; R F K I K Tc; (Dfck Sfck)mentioning

confidence: 99%

A Methodology for Grouping Source Terms for Consequence Calculations in Probabilistic Risk Assessments

1990

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“…Areview of PRAs for the Sequoyah, Zion, C-alvert Cliffs, and Oconee plants suggests a similar, if not as overwhelming, preponderance of risk-significant high pre~~urc vessel breach sequences (Payne eta!. 1984;Benjamin et al 1987;Wheeler 1986;NSAC 1984).…”

Section: Description Of the Strategymentioning

confidence: 99%

Identification and evaluation of PWR in-vessel severe accident management strategies

Dukelow

Harrison²,

Morgenstern

1992

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This reports documents work performed for the NRC/RES Accident Management Guidance Program to evaluate possible strategies for mitigating the consequences of PWR severe accidents. The selection and evaluation of strategies was limited to the in-vessel phase of the severe accident, i.e., after the initiation of core degradation and prior to RPV failure. A parallel project at BNL has been considering strategies applicable to the ex-vessel phase of PWR severe accidents.

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An exploratory sensitivity study with the MACCS reactor accident consequence model

Helton

Rollstin²,

Sprung

et al. 1992

Reliability Engineering & System Safety

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Evaluation of severe accident risks and the potential for risk reduction: Surry Power Station, Unit 1: Draft report for comment

Cited by 6 publications

References 0 publications

A Methodology for Grouping Source Terms for Consequence Calculations in Probabilistic Risk Assessments

A Methodology for Grouping Source Terms for Consequence Calculations in Probabilistic Risk Assessments

Identification and evaluation of PWR in-vessel severe accident management strategies

An exploratory sensitivity study with the MACCS reactor accident consequence model

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