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

https://doi.org/10.1115/ICONE18-29946

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.

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

Fission product release inventory analysis code for high-temperature gas-cooled reactor during accident, HTCORE

*; Suzuki, Katsuo; *;

JAERI-M 88-256, 47 Pages, 1988/12

JAERI-M-88-256.pdf:1.05MB

no abstracts in English

Evalution of Effective Coolant Flow in the Experimental VHTR Core at Detailed Design Stage II

; ; *; ;

JAERI-M 85-184, 105 Pages, 1985/11

JAERI-M-85-184.pdf:2.59MB

no abstracts in English

Analysis of SHE critical experiments by neutronic design codes for experimental very high temperature reactor

; ; ; *

Journal of Nuclear Science and Technology, 22(5), p.358 - 370, 1985/05

https://doi.org/10.3327/jnst.22.358

no abstracts in English

Nuclear Analysis of the Experimental VHTR Fuel Lattice

*; ; ;

JAERI-M 84-209, 38 Pages, 1984/11

JAERI-M-84-209.pdf:1.19MB

no abstracts in English

Design studies of Backup Core for the Experimtal Multi-purpose VHTR(2);Overall Characteristics of Backup Core with Semi-pin Type Fule Elements

; ; ; ; ; ; ; ; Suzuki, Katsuo;

JAERI-M 82-103, 137 Pages, 1982/09

JAERI-M-82-103.pdf:3.26MB

no abstracts in English

Analysis of Reactivity Worths of Burnable Poison Rods in SHE-14 - Accuracy Investigation of VHTR Nuclear Design Methods (5) -

; *; ;

JAERI-M 9956, 23 Pages, 1982/03

JAERI-M-9956.pdf:0.81MB

no abstracts in English

Analysis of Prompt Neutron Decay Constants of Critical and Control Rod Inserted States of SHE-14 -Accuracy Investigation of VHTR Nuclear Design Methods (3)-

; *; ;

JAERI-M 9942, 60 Pages, 1982/02

JAERI-M-9942.pdf:1.87MB

no abstracts in English

An Analysis of Copper Activation Reaction Rate Distribution of SHE-8 - Accuracy Investigation of VHTR Nuclear Design Method (4) -

; ; ;

JAERI-M 9912, 21 Pages, 1982/01

JAERI-M-9912.pdf:0.76MB

no abstracts in English