Results 11 to 20 of about 7,764 (263)

Research and Analysis of Thermal Parameter of Million-kilowatt Sodium-cooled Fast Reactor [PDF]

open access: yesYuanzineng kexue jishu
The million-kilowatt sodium-cooled fast reactor is a mature and commercially promising reactor type, playing a key role in the integrated closed sodium-cooled fast reactor nuclear energy system (integrated fast reactor).
DING Tongwei1, CHEN Wei2, WANG Wenjie3
doaj   +2 more sources

Semiempirical model for wet scrubbing of bubble rising in liquid pool of sodium-cooled fast reactor

open access: yesNuclear Engineering and Technology, 2018
Mechanistic calculations for wet scrubbing of aerosol/vapor from gas bubble rising in liquid pool are essential to safety of sodium-cooled fast reactor. Hence, scrubbing of volatile fission product from mixed gas bubble rising in sodium pool is presented
Arjun Pradeep, Anil Kumar Sharma
doaj   +2 more sources

Numerical evaluation of hypothetical core disruptive accident in full-scale model of sodium-cooled fast reactor

open access: yesNuclear Engineering and Technology, 2022
A hypothetical core destructive accident (HCDA) has received widespread attention as one of the most serious accidents in sodium-cooled fast reactors. This study combined recent advantages in numerical methods to realize realistic modeling of the complex
Zhihong Guo, Xiaodong Chen, Guoqing Hu
doaj   +2 more sources

Research Progress in Key Thermal-hydraulic Issue of Sodium-cooled Fast Reactor [PDF]

open access: yesYuanzineng kexue jishu
Sodium-cooled fast reactors are considered the preferred reactor type for fourth generation nuclear energy systems due to their high thermal efficiency, high fuel utilization efficiency, inherent safety, and unique advantages of achieving a closed fuel ...
YANG Hongyi1, XUE Xiuli1, , , ZHOU Zhiwei1, LIN Chao1, LI Hongrui2, GAO Xinzhao1, YU Xintai1, MA Xiao1, XIAO Yubai1, LUO Rui2
doaj   +2 more sources

Preliminary Study on Core Melt In-vessel Retention of Pool-type Sodium-cooled Fast Reactor

open access: yesYuanzineng kexue jishu
The inherent safety of reactor is emphasized in the design of the sodium-cooled fast reactors (SFRs). For accident mitigation, inherent safety and passive measures are adopted to reduce the demand for power sources and enhance safety and economy.
XUE Fangyuan1, ZHANG Donghui2, LIU Yizhe1, ZHANG Xisi1
doaj   +2 more sources

Effect of Distribution Header Pressure Drop on Flow Distribution of Assembly for Sodium-cooled Fast Reactor [PDF]

open access: yesYuanzineng kexue jishu
China is accelerating the development of sodium-cooled fast reactor technology. For nuclear reactors, whether it is a pressurized water reactor or a fast reactor, core flow distribution is a key concern, which directly determines whether the reactor can ...
LIN Chao, GAO Xinzhao, ZHOU Zhiwei, YU Xintai
doaj   +2 more sources

Research on Design of Natural Circulation Decay Heat Removal for Pool-type Sodium-cooled Fast Reactor [PDF]

open access: yesYuanzineng kexue jishu
Based 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
doaj   +2 more sources

On the Particle Swarm Optimization of cask shielding design for a prototype Sodium-cooled Fast Reactor

open access: yesNuclear Engineering and Technology, 2019
For the continuous operation of a nuclear reactor, burnt fuel needs to be replaced with fresh fuel, where appropriate (ex-vessel) fuel handling is required.
Dong-Won Lim   +3 more
doaj   +2 more sources

Physical characteristics of large fast-neutron sodium-cooled reactors with advanced nitride and metallic fuels

open access: yesNuclear Energy and Technology, 2015
Mixed nitride uranium–plutonium fuel is the most attractive and advanced type of fuel for fast-neutron sodium-cooled reactors, and is considered as the base fuel for future commercial fast-neutron power reactors.
V.I. Matveev   +2 more
doaj   +2 more sources

Minor actinides impact on basic safety parameters of medium-sized sodium-cooled fast reactor

open access: yesNukleonika, 2015
An analysis of the influence of addition of minor actinides (MA) to the fast reactor fuel on the most important safety characteristics was performed.
Darnowski Piotr, Uzunow Nikolaj
doaj   +3 more sources

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