Safety Evaluation Of Indian Nuclear Power Plants Post Fukushima Incident

B Passive core cooling by natural circulation A FUELLING MACHINE AIRLOCK REACTOR BUILDING STEAM GENERATOR PHT PUMP REACTIVITY MECHANISMS SRVS ASDVS H.P. TURBINE MSIVS MOISTURE SEPARATOR REHEATERS L.P. TURBINE GENERATOR CSDVS DEAERA TING HEATERS CONDENSER COOLING WATER GENERATOR TRANSFORMERS HP. HEATERS BFPs L.P. HEATERS CEPS COOLING WATER EQUIPMENT STEAM CONDENSATE FEED WATER PHT MODERATOR ELECTRICAL Schematic Diagram of Indian PHWR as Elevation difference between Steam Generators (B) and Reactor Core (A) provides driving force for natural circulation of coolant known Thermosyphoning. Through this phenomenon decay heat is removed by supplying fire water to steam generator.

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