Analysis of Thermal and Irradiation Behaviour of Fuelled Graphite Bricks for a High Temperature Gas Cooled Reactor

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dc.contributor.authorV.S. Beckett
dc.date.accessioned2016-10-10T18:46:18Z
dc.date.available2016-10-10T18:46:18Z
dc.date.issued1971-09-20T00:00:00+00:00
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/28904
dc.publisherIASMiRT
dc.relation.ispartofseriesD - Fuel Elements
dc.relation.ispartofseriesD2 - Stress Analysis of Graphite Fuel/Moderator Elements-I
dc.relation.ispartofseriesSMiRT 1 - Berlin, Germany. September 20-24, 1971
dc.titleAnalysis of Thermal and Irradiation Behaviour of Fuelled Graphite Bricks for a High Temperature Gas Cooled Reactor
dc.typeConference Proceeding

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1971 - SMiRT 1 - Berlin, Germany