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dc.contributor.authorSawdye, Robert Williamen_US
dc.contributor.authorKazimi, Mujid S.en_US
dc.contributor.otherUnited States. Department of Energyen_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.date.accessioned2014-09-12T23:54:02Z
dc.date.available2014-09-12T23:54:02Z
dc.date.issued1978en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/89513
dc.description"July 1978."en_US
dc.descriptionOriginally presented as the first author's thesis, (M.S.)--in the M.I.T. Dept. of Nuclear Engineering, 1978en_US
dc.descriptionIncludes bibliographical references (pages 87-89)en_US
dc.description.abstractA methodology has been developed to provide system reliability criteria based on an assessment of the potential radiological hazards associated with a fusion reactor design and on hazard constraints which prevent fusion reactors from being more hazardous than light water reactors. The probabilistic consequence analyses, to determine the results of radioactivity releases, employed the consequence model developed to assess the risks associated with light water reactors for the Reactor Safety Study. The calculational model was modified to handle the isotopes induced in the structural materials of two conceptual Tokamak reactor designs, UWMAK-I and UWMAK-III. Volatile oxidation of the first wall during a lithium fire appears to be a primary means of disrupting induced activity, and the molybdenum alloy, TZM (UWMAK-III), tends to be more susceptible than 316 stainless steel (UWMAK-I) to mobilization by this mechanism. It was determined that the radiological!  hazards associated with induced activity in these reactor designs imply reliability requirements comparable to those estimated for light water reactors. The consequences of estimated maximum possible releases of induced activity, however, are substantially less than the maximum light water reactor accident consequences.en_US
dc.description.sponsorshipReport issued under contract, U.S. Dept. of Energy EY-76-02-2431en_US
dc.format.extent108 pagesen_US
dc.publisherCambridge. Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1978]en_US
dc.relation.ispartofseriesMITNE ; no. 220en_US
dc.subject.lccTK9008.M41 N96 no.220en_US
dc.subject.lcshFusion reactorsen_US
dc.subject.lcshNuclear reactors -- Safety measuresen_US
dc.titleApplication of probabilistic consequence analysis to the assessment of potential radiological hazards of fusion reactorsen_US
dc.typeTechnical Reporten_US
dc.identifier.oclc04759949en_US


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