ASME STP-NU-009 PDF
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STP NU 009 Graphite for High Temperature Gas Cooled Nuclear Reactors
Description
Basic information relative to bulk graphite production, structure, chemical properties, physical properties and neutron irradiation behavior.
View additional information technical report presents basic relative bulk graphite production, structure, chemical properties, physical properties neutron irradiation behavior. characteristics, manufacture, behavior well new generation nuclear grades briefly reviewed. overview moderated gas-cooled reactor designs also presented. serves summary training seminar conducted asme boiler pressure vessel code week, october 30–november 3, 2006, louisville, ky. no universally accepted design moderator structures. history reactors traced beginnings 1942 recent utility start-up 1989. developments continued intervening years especially area helium cooled high temperature reactors. prismatic 30mwth, pebble-bed 10mwth, test brought operation japan china, respectively.
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