Begell House作者，编辑及审稿者

Sameer Hajela

Directorate of Reactor Safety & Analysis, Nuclear Power Corporation of India Limited Nabhikiya Urja Bhavan, Anushakti Nagar, Mumbai, Maharashtra, PIN-400094, India
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Articles

EVALUATION OF FUNCTIONAL ADEQUACY OF ELECTRICALLY OPERATED INSTRUMENTED RELIEF VALVES OF PRIMARY HEAT TRANSPORT SYSTEM FOR 700MWE INDIAN PRESSURIZED HEAVY WATER REACTOR Vol. 0 '2017 - Proceedings of the 24th National and 2nd International ISHMT-ASTFE Heat and Mass Transfer Conference (IHMTC-2017)
SIMULATION OF NATURAL CIRCULATION FLOW DURING POWER MANEUVERING IN MASLWR TEST FACILITY WITH COMPUTER CODE RELAP-5/MOD3.2 Vol. 0 '2017 - Proceedings of the 24th National and 2nd International ISHMT-ASTFE Heat and Mass Transfer Conference (IHMTC-2017)
TRANSIENT ANALYSIS OF INADVERTENT CLOSURE OF BLEED CONDENSER LEVEL CONTROL VALVES OF 700 MWE INDIAN PRESSURIZED HEAVY WATER REACTOR Vol. 0 '2017 - Proceedings of the 24th National and 2nd International ISHMT-ASTFE Heat and Mass Transfer Conference (IHMTC-2017)
Transient Analysis Of All Steam Generators Feed Valve Stuck Open For 700 MWe IPHWRs Vol. 0 '2019 - Proceedings of the 25th National and 3rd International ISHMT-ASTFE Heat and Mass Transfer Conference (IHMTC-2019)
Assessment of Shutdown Systems' performance during postulated Large Break LOCA for 700MWe Pressurized Heavy Water Reactors Vol. 0 '2021 - Proceedings of the 26thNational and 4th International ISHMT-ASTFE Heat and Mass Transfer Conference December 17-20, 2021, IIT Madras, Chennai-600036, Tamil Nadu, India
Optimization Of Critical Opening In Between Different Compartment of Containment For Future 700 MWe IPHWRS Vol. 0 '2024 - Proceedings of the 27th National and 5th International ISHMT-ASTFE Heat and Mass Transfer Conference December 14-17, 2023, IIT Patna, Patna-801106, Bihar, India