Stress Analysis of a Graphite Fuel Element for HTR under Fast Neutron Irradiation

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dc.contributor.authorZ. Zhang
dc.contributor.authorD. Duo
dc.date.accessioned2016-10-10T18:37:17Z
dc.date.available2016-10-10T18:37:17Z
dc.date.issued1991-08-18T00:00:00+00:00
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/22955
dc.publisherIASMiRT
dc.relation.ispartofseriesC - Fuel and Core Structures
dc.relation.ispartofseriesC02 - Fuel Element Structural Analysis (II)
dc.relation.ispartofseriesSMiRT 11 - Tokyo, Japan. August 18-23, 1991
dc.titleStress Analysis of a Graphite Fuel Element for HTR under Fast Neutron Irradiation
dc.typeConference Proceeding

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1991 - SMiRT 11 - Tokyo, Japan