An overview of thermal hydraulic design validation studies for AHWR
Bagul, R.K.; Sharma, M.; Pilkhwal, D.S.; Vijayan, P.K.; Sinha, R.K.
International conference on Future of Heavy Water Reactors (HWR-FUTURE)2011
International conference on Future of Heavy Water Reactors (HWR-FUTURE)2011
AbstractAbstract
[en] Core heat removal by natural circulation under the operating as well as accidental conditions is one of the several passive safety features of the Advanced Heavy Water Reactor (AHWR) being developed in India. Integral Test Loop (ITL) is an experimental test facility which simulates the Main Heat Transport System and safety systems of AHWR. Several experiments have been carried out to validate the thermal-hydraulic design features of AHWR such as flow stability during startup, LOCA and performance of Isolation Condensers to remove decay heat using natural circulation. This paper presents an overview of these experimental studies. (author)
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Canadian Nuclear Society, Toronto, Ontario (Canada); 81.5 Megabytes; ISBN 978-1-926773-07-0; ; 2011; [15 p.]; International conference on Future of Heavy Water Reactors; Ottawa, Ontario (Canada); 2-5 Oct 2011; Available from the Canadian Nuclear Society, Toronto, Ontario (Canada); Paper 006, 13 refs., 35 figs.
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Miscellaneous
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Conference
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Descriptors (DEI)
Descriptors (DEC)
ACCIDENTS, CONVECTION, COOLING SYSTEMS, ENERGY SYSTEMS, ENERGY TRANSFER, FLUID MECHANICS, HEAT TRANSFER, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, HYDRAULICS, MASS TRANSFER, MECHANICS, POWER REACTORS, PRESSURE TUBE REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, THERMAL REACTORS
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