Results 41 to 50 of about 24,364 (164)

Analysis of transient characteristics and design improvement of the passive residual heat removal system of NHR-200-II

Frontiers in Energy Research
NHR-200-II is a small integrated pressurized water reactor with 200 MW core thermal power. The core heat is transferred to two independent intermediate circuits via fourteen in-vessel primary heat exchangers (PHE), and the heat in the intermediate ...
Geng Yiwa, Liu Xiongbin, Li Ziyi, Huang Shuliang, Zhou Lanyu, Xue Yanfang, Li Xiaotian, Zhang Yajun   +7 more
doaj   +1 more source

Development of probabilistic risk assessment methodology of decay heat removal function against combination hazard of low temperature and snow for sodium-cooled fast reactors

Mechanical Engineering Journal, 2018
A probabilistic risk assessment (PRA) should be performed not only for earthquake and tsunami which are major natural events in Japan but also for other natural external hazards. However, PRA methodologies for other external hazards and their combination
Hiroyuki NISHINO, Hidemasa YAMANO, Kenichi KURISAKA   +2 more
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Modeling of natural circulation for the inherent safety analysis of sodium cooled fast reactors

Nuclear Energy and Technology, 2016
The paper discusses a set of developed integrated one-dimensional models of thermal-hydraulic processes that contribute to the removal of decay heat in a BN-type reactor.
A.S. Bochkarev, P.N. Alekseev, A.S. Korsun, V.S. Kharitonov   +3 more
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Hybrid medium model for conjugate heat transfer modeling in the core of sodium-cooled fast reactor

Nuclear Engineering and Technology, 2020
Core-wide temperature distribution in sodium-cooled fast reactor plays a key role in its decay heat removal process, however the prediction for temperature distribution is quite complex due to the conjugate heat transfer between the assembly flow and the
X.A. Wang, Dalin Zhang, Mingjun Wang, Ping Song, Shibao Wang, Yu Liang, Yapei Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su   +9 more
doaj   +1 more source

Heat transfer intensification in emergency cooling heat exchanger and dry cooling towers on nuclear power plant using air-water mist flow [PDF]

Nuclear Energy and Technology, 2019
Advanced nuclear power plants are equipped with passive emergency heat removal systems (PEHRS) for removing the decay heat from reactor equipment in accidents accompanied by primary circuit leakage to the final heat absorber (ambient air).
Akram H. Abed, Sergey E. Shcheklein, Valery M. Pakhaluev   +2 more
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The effect of storage conditions and computer model simplification on the thermal state of the RBMK-1500M2 cask

Nuclear Engineering and Technology
Interim storage of spent nuclear fuel is a very important part of the overall nuclear power generation cycle. At Ignalina NPP, spent nuclear fuel is stored in interim storage facilities in specially designed casks before being transferred to a geological
Kęstutis Račkaitis, Povilas Poškas, Robertas Poškas, Hussam Jouhara   +3 more
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ROLE OF PASSIVE SAFETY FEATURES IN PREVENTION AND MITIGATION OF SEVERE PLANT CONDITIONS IN INDIAN ADVANCED HEAVY WATER REACTOR

Nuclear Engineering and Technology, 2013
Pressing demands of economic competitiveness, the need for large-scale deployment, minimizing the need of human intervention, and experience from the past events and incidents at operating reactors have guided the evolution and innovations in reactor ...
VIKAS JAIN, A.K. NAYAK, M. DHIMAN, P.P. KULKARNI, P.K. VIJAYAN, K.K. VAZE   +5 more
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Research and development of probabilistic risk assessment methodology for combination event of low temperature and snow

Nihon Kikai Gakkai ronbunshu, 2016
The objective of this study is to develop probabilistic risk assessment (PRA) methodology for combination event of low temperature and snow by focusing on decay heat removal system (DHRS) of sodium-cooled fast reactor.
Hiroyuki NISHINO, Hidemasa YAMANO, Kenichi KURISAKA   +2 more
doaj   +1 more source

Study on In-Vessel Retention (IVR) of unprotected accident for fast reactor ((2) Assessment of PAMR/PAHR phase in ULOF)

Nihon Kikai Gakkai ronbunshu, 2017
The achievement of In-Vessel Retention (IVR) of the accident consequences in an unprotected loss of flow (ULOF), which is one of the technically inconceivable events postulated beyond design basis, is effective and rational approach in enhancing the ...
Joji SOGABE, Tohru SUZUKI, Yusaku WADA, Yoshiharu TOBITA   +3 more
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Preliminary Study on Core Melt In-vessel Retention of Pool-type Sodium-cooled Fast Reactor

Yuanzineng 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   +1 more source