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Journal Articles

Analysis of operating experience involving loss of decay heat removal during reactor shutdown in pressurized water reactors

Watanabe, Norio; Hirano, Masashi

Journal of Nuclear Science and Technology, 29(12), p.1212 - 1223, 1992/12

no abstracts in English

JAEA Reports

Analysis of operating experience data in nuclear power plants; Loss of decay heat removal during reactor shutdown

Watanabe, Norio; Hirano, Masashi;

JAERI-M 91-143, 173 Pages, 1991/09

JAERI-M-91-143.pdf:5.72MB

no abstracts in English

Oral presentation

Research and development of margin assessment methodology of decay heat removal function against external hazards, 9; Forest fire hazard assessment methodology

Okano, Yasushi; Yamano, Hidemasa

no journal, , 

There has been an increased concern in the safety of NPP for external hazards, one of which is a forest fire. Conventional forest fire assessments have been performed with deterministic and conservative manner, using so-called envelope initial and boundary conditions on forest fire analyses. In this study, the forest fire hazard assessment methodology, which is subject to an external-hazard probabilistic risk assessment (PRA), is being developed in order to quantitatively evaluate frequency and consequence of the forest fire that has a potential impact on a NPP and then to obtain the Core Damage Frequency. The new methodology based on a logic tree is developed in this study, as well as the sensibility analyses on weather conditions.

Oral presentation

Research and development of margin assessment methodology of decay heat removal function against external hazards, 8; Event sequence assessment methodology against wind hazard

Kurisaka, Kenichi; Yamano, Hidemasa; Nishino, Hiroyuki

no journal, , 

This study aims at developing the probabilistic risk assessment methodology of decay heat removal function in sodium-cooled fast reactor systems against wind hazard. For this purpose, wind hazard curve was evaluated; event trees were developed to identify the strong wind induced core damage sequence; core damage frequency was quantified, and dominant sequence was evaluated.

Oral presentation

Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor, 5; Validation of reactor analytical model for PLOHS events

Mori, Takero; Ohira, Hiroaki; Sotsu, Masutake; Fukano, Yoshitaka

no journal, , 

In order to evaluate the availability of the decay heat removal by natural circulation which is a measure for the Protected Loss of Heat Sink (PLOHS) in Fast Reactor, a whole core model which could simulate thermal hydraulics of each subassembly in a reactor was applied to Monju core. The Monju core model was validated by a test result of actual plant, MONJU. In addition, an analysis was conducted for PLOHS to investigate the applicability of this model.

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