Results 31 to 40 of about 24,364 (164)
Neutronic analysis of a heat-pipe cooled reactor
Acta Polytechnica CTU Proceedings, 2023 Heat-pipe cooled reactors belong to the group of nuclear reactors using heat pipes filled with liquid metals (such as sodium or potassium) to cool the core. Due to the passive heat removal system, there is no need to use closed loops with pumps, and the
Josef Sabol, Jan Frýbort
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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.)
openaire +2 more sources
Gas-Cooled Fast Reactor (GFR) Decay Heat Removal Concepts [PDF]
, 2005 Current research and development on the Gas-Cooled Fast Reactor (GFR) has focused on the design of safety systems that will remove the decay heat during accident conditions, ion irradiations of candidate ceramic materials, joining studies of oxide dispersion strengthened alloys; and within the Advanced Fuel Cycle Initiative (AFCI) the fabrication of ...
Weaver, K. D. +3 more
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PENINGKATAN KINERJA SISTEM KESELAMATAN PASIF PADA REAKTOR NUKLIR DENGAN PENAMBAHAN KOMPONEN RVACS
Jurnal Pendidikan Fisika Indonesia, 2014 Kelengkapan sistem keselamatan pasif dan inheren pada reaktor lanjut merupakan prasyarat utama. Makalah ini mengeksplorasi hasil desain konseptual sistem pembuang sisa panas pada pusat listrik tenaga nuklir berjenis Very High-Temperature Reactor.
A. G. Abdullah +2 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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Nuclear Engineering and Technology, 2015 Twenty sodium-cooled fast reactors (SFRs) have provided valuable experience in design, licensing, and operation. This paper summarizes the important safety criteria and safety guidelines of intermediate sodium systems, steam generators, decay heat ...
Subhash Chander Chetal
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Yuanzineng kexue jishuBased on the design parameters of the core decay heat removal through natural circulation of the typical high-power sodium-cooled fast reactor, using the system analysis program ERAC, a detailed analysis of the reactor core decay heat removal process ...
ZHOU Zhiwei, XUE Xiuli, LIN Chao, YU Xintai, YANG Yong, YANG Hongyi
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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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Natural circulation characteristics of main loop after shutdown of liquid-fuel molten salt reactor
He jishuBackgroundThe molten salt reactor (MSR) is one of the six advanced reactors identified by the Generation IV International Forum. The MSR exhibits unique characteristics, such as intrinsic safety, sustainable development, nuclear nonproliferation, natural
XUE Shuaiyu +3 more
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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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