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AbstractAbstract
[en] The design of the reactor pressure vessel is an important issue in the VHTR design due to its high operating temperature. The extensive experience base in Light Water Reactor makes SA508/533 steel emerge as a strong candidate for the VHTR reactor vessel but requires maintaining the vessel temperature below the ASME code limit. To meet the temperature requirement, three types of vessel cooling options for a prismatic core VHTR are considered: an internal vessel cooling, an external vessel cooling, and an internal insulation. The performances of the vessel cooling options are evaluated by using a system thermo-fluid analysis code and a commercial computational fluid dynamics code during normal operation and accidents. The results suggested that the internal vessel cooling with the modified inlet flow path will be a promising option. The external cooling option does not ensure an effective cooling of the RPV. The insulation option provides an effective reduction of the RPV temperature in the normal and accident conditions but reduces the fuel safety margin during the accidents, requiring careful consideration before the implementation.
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S0306-4549(10)00278-1; Available from http://dx.doi.org/10.1016/j.anucene.2010.08.007; Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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Country of publication
ALLOYS, CARBON ADDITIONS, CONTAINERS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, FUELS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HELIUM COOLED REACTORS, HIGH ALLOY STEELS, HTGR TYPE REACTORS, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS, MECHANICS, POWER REACTORS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, SIMULATION, STEELS, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS
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