Results 21 to 30 of about 21,387 (164)
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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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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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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Nuclear Engineering and Technology, 2016 To get an insight into the operating characteristics of the passive residual heat removal system of molten salt reactors, a two-phase natural circulation test facility was constructed.
Xiangcheng Wu +6 more
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Yuanzineng kexue jishu, 2023 The concept of the inherent safety characteristic on thermal-hydraulic of the pool-type sodium-cooled fast reactor was proposed and its formation mechanism was analyzed.
ZHOU Zhiwei;XUE Xiuli;YANG Yong;YANG Hongyi
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Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors
Science and Technology of Nuclear Installations, 2009 The safety goal of the current designs of advanced high-temperature thermal gas-cooled reactors (HTRs) is that no core meltdown would occur in a depressurization event with a combination of concurrent safety system failures.
Lap-Yan Cheng, Thomas Y. C. Wei
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Nuclear Engineering and Technology, 2013 As passive safety features for nuclear power plants receive increasing attention, various studies have been conducted to develop safety systems for 3rd-generation (GEN-III) nuclear power plants that are driven by passive systems.
YUN-JE CHO +5 more
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CFD Analysis of the Passive Decay Heat Removal System of an LBE-Cooled Fast Reactor
Science and Technology of Nuclear Installations, 2018 This paper presents capacity of the passive decay heat removal system (DHRS) operated under the natural circulation conditions to remove decay heat inside the main vessel of the Lead-bismuth eutectic cooled Fast Reactor (LFR).
Jiarun Mao +5 more
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