An Evaluation of Korean Next Generation Reactor Pressure Vessel Neutron Fluence by Monte Carlo Simulations

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dc.contributor.authorKim, Jong Kyung
dc.contributor.authorShin, Chang Ho
dc.contributor.authorPark, Sung-Ho
dc.contributor.authorPark, Goon-Cherl
dc.contributor.authorLee, Jae-Hun
dc.date.accessioned2016-10-10T18:49:09Z
dc.date.available2016-10-10T18:49:09Z
dc.date.issued2001-08-12T00:00:00+00:00
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/30905
dc.publisherIASMiRT
dc.relation.ispartofseriesS - Advanced Reactors
dc.relation.ispartofseriesS01 -
dc.relation.ispartofseriesSMiRT 16 - Washington, DC, USA. August 12-17, 2001
dc.titleAn Evaluation of Korean Next Generation Reactor Pressure Vessel Neutron Fluence by Monte Carlo Simulations
dc.typeConference Proceeding

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2001 - SMiRT 16 - Washington, DC, USA