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Journal Articles

A Technical overview of the Japan's standards for risk-informed decision making

Narumiya, Yoshiyuki*; Hirano, Mitsumasa*; Hirano, Masashi

Proceedings of 18th International Conference on Nuclear Engineering (ICONE-18) (CD-ROM), 7 Pages, 2010/05

Over the last thirty years, there have been many accomplishments throughout the world with regard to severe accident studies and the development and application of the PSA techniques. Based on the results and experience gained from these efforts, it is necessary to shift the emphasis toward risk-informed decision-making (RIDM) in Japan. In this context, the Atomic Energy Society of Japan (AESJ) has developed an implementation standard for RIDM. In this report, the content and background of the standard are summarized.

JAEA Reports

Core dynamics analysis code for high temperature gas reactor; BLOOST-J2

Nakagawa, Shigeaki; Mitake, Susumu*; Ohashi, Kazutaka*; Hirano, Mitsumasa

JAERI-M 89-013, 44 Pages, 1989/02

JAERI-M-89-013.pdf:0.96MB

no abstracts in English

JAEA Reports

Two-dimensional thermal analysis code "TAC-NC" for high temperature engineering test reactor and its verification

Kunitomi, Kazuhiko; Nakagawa, Shigeaki; Suzuki, Katsuo; Wada, Hozumi*; Hirano, Mitsumasa

JAERI-M 89-001, 34 Pages, 1989/02

JAERI-M-89-001.pdf:0.86MB

no abstracts in English

Oral presentation

Reliability enhancement of seismic risk assessment of NPP as risk management fundamentals, 1; Program plan and objectives

Muramatsu, Ken*; Takada, Tsuyoshi*; Itoi, Tatsuya*; Nishida, Akemi; Uchiyama, Tomoaki*; Furuya, Osamu*; Fujimoto, Shigeru*; Hirano, Mitsumasa*; Muta, Hitoshi*

no journal, , 

In this research project, study on probabilistic models and treatment of epistemic uncertainty, study on quantification of epistemic uncertainty on fragility assessment and verification of usefulness of proposed method are performed for reliability enhancement of seismic risk assessment. In this report, program plan and objectives are shown as part 1.

Oral presentation

Study on reliability enhancement of seismic risk assessment of NPP, 1; Program plan and development of new framework of probabilistic models

Muramatsu, Ken*; Furuya, Osamu*; Fujimoto, Shigeru*; Hirano, Mitsumasa*; Muta, Hitoshi*; Takada, Tsuyoshi*; Itoi, Tatsuya*; Nishida, Akemi; Uchiyama, Tomoaki*

no journal, , 

This project, focusing on uncertainty assessment framework and utilization of expertise, and finally developing relevant computer codes to improve reliability of seismic probabilistic risk assessment (SPRA) and to promote its further use of the SPRA, develops methodology for quantification of uncertainty associated with final results from SPRA in the framework of risk management of NPP facilities. The following scopes are set. (1) Development of framework of probabilistic models for uncertainty quantification and Computer codes (2) Aggregation of expert opinion on structure/equipment fragility estimation and development of implementation guidance on epistemic uncertainty (modeling uncertainty) (3) Study on applicability of SPRA to model plant. In this report, program plan of our research and new probabilistic models and treatment of epistemic uncertainty will be explained as part 1.

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