Results 41 to 50 of about 21,387 (164)

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

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
doaj   +1 more source

A conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability

Mechanical Engineering Journal, 2020
The authors are developing the design concept of the pool-type sodium-cooled fast reactor (SFR) that addresses Japan’s specific siting conditions such as earthquakes and meets safety design criteria (SDC) and safety design guidelines (SDG) for Generation
Shigenobu KUBO, Yoshitaka CHIKAZAWA, Hiroyuki OHSHIMA, Masato UCHITA, Takayuki MIYAGAWA, Masao ETO, Tetsuji SUZUNO, Ichiyo MATOBA, Junji ENDO, Osamu WATANABE, Koichi HIGURASHI   +10 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
doaj   +1 more source

Verification of the ability of safe activation of the isolated DHR loop of the ALLEGRO reactor in the event of an accident with complete loss of power

Nuclear Engineering and Technology
The development of the ALLEGRO gas-cooled demonstration reactor dates back to the early days of Generation 4 reactors. A more detailed conceptual design is currently being developed, which includes thermohydraulic studies of the reactor's safety features.
Pavel Zácha, Václav Železný
doaj   +1 more source

Risk-informed approach to the safety improvement of the reactor protection system of the AGN-201K research reactor

Nuclear Engineering and Technology, 2020
Periodic safety reviews (PSRs) are conducted on operating nuclear power plants (NPPs) and have been mandated also for research reactors in Korea, in response to the Fukushima accident.
Ibrahim Ahmed, Enrico Zio, Gyunyoung Heo
doaj   +1 more source

Experimental Evaluation of the Ventilation Effectiveness of Corner Stratum Ventilation in an Office Environment

Buildings, 2019
An experimental study was conducted in a room resembling an office in a laboratory environment. The study involved investigating the ability of corner-placed stratum ventilation in order to evaluate the ventilation’s effectiveness and local thermal
Arman Ameen, Gasper Choonya, Mathias Cehlin   +2 more
doaj   +1 more source

Numerical simulations of forest fire propagation and smoke transport as an external hazard assessment methodology development for a nuclear power plant

Mechanical Engineering Journal, 2016
A new method has been developed to assess potential challenges by forest fire smoke on a cooling function of a decay heat removal system (DHRS) of a sodium-cooled fast reactor.
Yasushi OKANO, Hidemasa YAMANO
doaj   +1 more source

Experimental Analysis of the Helium Loop Steady States [PDF]

MATEC Web of Conferences
Nuclear power is one of the most cost-effective and productive sources of energy. Nuclear power plants contribute significantly to global electricity production. A factor preventing their further expansion is their overall safety.
Knížat Branislav, Olšiak Róbert, Mlkvik Marek, Vach Matej   +3 more
doaj   +1 more source

Inherent safety evaluation of a long-life fast reactor (SALUS-100) under unprotected loss of heat sink conditions

Nuclear Engineering and Technology
The Korea Atomic Energy Research Institute (KAERI) is developing the long-life sodium-cooled fast reactor SALUS-100, designed for continuous 20-year operation without refueling. The concept adapts the proven technology of the Prototype Generation-IV SFR (
Junkyu Han, Nam-il Tak, Sun Rock Choi, Hyun-Sik Park, Jonggan Hong, Ji-woong Han, In Sub Jun, Huee-Youl Ye, Jeong Ik Lee   +8 more
doaj   +1 more source