Results 21 to 30 of about 183,014 (291)
CFD Investigation of MHTGR Natural Circulation and Decay Heat Removal in P-LOFC Accident
Frontiers in Energy Research, 2020 One of the key postulated accidents in a high-temperature gas-cooled reactor (HTGR) is the pressurized loss of forced cooling (P-LOFC) of the primary loop, which can be triggered by its primary helium circulator trip or turbine trip.
Chengqi Wang +2 more
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Characteristic analysis of natural circulation residual heat removal in small reactor
International Journal of Advanced Nuclear Reactor Design and Technology, 2022 In order to study the characteristics of small helium-xenon cooled nuclear reactor that only relies on natural circulation to remove residual heat after shutdown, this paper carries out geometric and physical modeling of helium-xenon cooled nuclear ...
Haoyang Liao +5 more
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Analysis on inadvertent operation of decay heat removal system in NuScale reactor [PDF]
AIP Conference Proceedings, 2019 Analysis on inadvertent operation of decay heat removal system in NuScale reactor has been carried out through numerical simulations using the RELAP5 code. The model used includes primary system, secondary system, decay heat removal system (DHRS) and water pool. Simulation begins with an opening of single DHRS train isolation valve when reactor runs at
null Susyadi +3 more
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Post-test simulation of a PLOFA transient test in the CIRCE-HERO facility [PDF]
, 2019 CIRCE is a lead–bismuth eutectic alloy (LBE) pool facility aimed to simulate the primary system of a heavy liquid metal (HLM) cooled pool-type fast reactor.
Caruso G. +4 more
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DECAY HEAT REMOVAL SYSTEM SYSTEM DESCRIPTION NO. 8 [PDF]
, 1956 The decay heat removal system of the PWR is described. (T.R.H.)
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Thermal Characteristics of High Temperature Naturally Circulating Helium Cooling Loop
Journal of Mechanical Engineering, 2018 The paper deals with the process properties in terms of the heat transfer, i.e. the thermal performance of the thermal-process units within a helium loop intended for the testing of the decay heat removal (DHR) from the model of the gas-cooled fast ...
Dzianik František +2 more
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Pre-test analysis of protected loss of primary pump transients in CIRCE-HERO facility [PDF]
, 2017 In the frame of LEADER project (Lead-cooled European Advanced Demonstration Reactor), a new configuration of the steam generator for ALFRED (Advanced Lead Fast Reactor European Demonstrator) was proposed. The new concept is a super-heated steam generator,
Caruso, G. +4 more
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Decay Heat Removal and Transient Analysis in Accidental Conditions in the EFIT Reactor
Science and Technology of Nuclear Installations, 2008 The development of a conceptual design of an industrial-scale transmutation facility (EFIT) of several 100 MW thermal power based on accelerator-driven system (ADS) is addressed in the frame of the European EUROTRANS Integral Project. In normal operation,
Giacomino Bandini +5 more
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Yuanzineng kexue jishuThe sodium-cooled fast reactor is one of the important reactor types of the fourth-generation advanced nuclear energy system. The safety of sodium-cooled fast reactors is improved by introducing a new passive decay heat removal system.
LU Daogang1, 2, SONG Haijie1, 2, GUO Jinsong1, 2, ZHAO Haiqi1, 2, ZHANG Yuhao1, 2, , , SUI Danting1, 2
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Hydrodynamic Properties of High Temperature Natural Circulating Helium Cooling Loop
Journal of Mechanical Engineering, 2017 The paper deals with the hydrodynamic properties, i.e. the consumption of mechanical energy expressed by pressure drops within a helium loop intended for the testing of decay heat removal (DHR) from the model of a gas-cooled fast reactor (GFR).
Dzianik František, Gužela Štefan
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