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dc.contributor.advisorSmith, Craig F.
dc.contributor.authorCan, Levent
dc.date.accessioned2012-03-14T17:35:02Z
dc.date.available2012-03-14T17:35:02Z
dc.date.issued2006-12
dc.identifier.urihttps://hdl.handle.net/10945/2379
dc.description.abstractlack of consensus among the world researchers on the significance of Po-210 build up in lead cooled reactors. The second objective is to evaluate the advantages and disadvantages of selected candidate metal coolants. In addressing both objectives, the computer code ORIGEN was used. To establish the background basis for these assessments, fundamental concepts of reactor physics are reviewed and discussed.en_US
dc.description.urihttp://archive.org/details/analysisofcoolan109452379
dc.format.extentxvi, 71 p. : ill. ;en_US
dc.publisherMonterey, California. Naval Postgraduate Schoolen_US
dc.subject.lcshPhysicsen_US
dc.subject.lcshTinen_US
dc.subject.lcshRadioactivityen_US
dc.subject.lcshLiquid metalsen_US
dc.subject.lcshLeaden_US
dc.subject.lcshNuclear reactorsen_US
dc.subject.lcshSodiumen_US
dc.titleAnalysis of coolant options for advanced metal cooled nuclear reactorsen_US
dc.typeThesisen_US
dc.contributor.secondreaderMaruyama, Xavier
dc.contributor.corporateNaval Postgraduate School (U.S.).
dc.contributor.departmentPhysics
dc.identifier.oclc80951324
etd.thesisdegree.nameM.S.en_US
etd.thesisdegree.levelMastersen_US
etd.thesisdegree.disciplineApplied Physicsen_US
etd.thesisdegree.grantorNaval Postgraduate Schoolen_US
etd.verifiednoen_US
dc.description.distributionstatementApproved for public release; distribution is unlimited.


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