Show simple item record

dc.contributor.authorParkinson, William
dc.contributor.authorRasmussen, Norman C.
dc.contributor.authorHinkle, William D.
dc.date.accessioned2006-12-19T15:55:53Z
dc.date.available2006-12-19T15:55:53Z
dc.date.issued1979-01
dc.identifier.other06851211
dc.identifier.urihttp://hdl.handle.net/1721.1/35157
dc.descriptionOriginally presented as the first author's thesis, (M.S.) in the M.I.T. Dept. of Nuclear Engineering, 1979.en
dc.description.abstractThe Reactor Safety Study (RSS) or Wash-1400 developed a methodology estimating the public risk from light water nuclear reactors. In order to give further insights into this study, a sensitivity analysis has been performed to determine the significant contributors to risk for both the PWR and BWR. The sensitivity to variation of the point values of the failure probabilities reported in the RSS was determined for the safety systems identified therein, as well as for many of the generic classes from which individual failures contributed to system failures. Increasing as well as decreasing point values were considered. An analysis of the sensitivity to increasing uncertainty in system failure probabilities was also performed. The sensitivity parameters chosen were release category prob- abilities, core melt probability, and the risk parameters of early fatalities, latent cancers and total property damage. The latter three are adequate for describing all public risks identified in the RSS. The results indicate reductions of public risk by less than a factor of two for factor reductions in system or generic failure probabilities as hignh as one hundred. There also appears to be more benefit in monitoring the most sensitive systems to verify adherence to RSS failure rates than to backfitting present reactors. The sensitivity analysis results do indicate, however, possible benefits in reducing human error rates.en
dc.description.sponsorshipFinal report for research project sponsored by Northeast Utilities Service Company, Yankee Atomic Electric Company under the M.I.T. Energy Laboratory Electric Utility Program.en
dc.format.extent9156752 bytes
dc.format.mimetypeapplication/pdf
dc.language.isoen_USen
dc.publisherMIT Energy Laboratoryen
dc.relation.ispartofseriesMIT-ELen
dc.relation.ispartofseries79-008en
dc.subjectNuclear reactors |x Safety measures.en
dc.subjectBoiling water reactors.en
dc.subjectPressurized water reactors.en
dc.titleSensitivity analysis of the reactor safety studyen
dc.typeTechnical Reporten


Files in this item

Thumbnail
Thumbnail
Thumbnail
Thumbnail

This item appears in the following Collection(s)

Show simple item record