Interim activity status report of "the group for investigation of reasonable safety assurance based on graded approach" (from September, 2019 to September, 2020)

Yonomoto, Taisuke; Nakashima, Hiroshi*; Sono, Hiroki; Kishimoto, Katsumi; Izawa, Kazuhiko; Kinase, Masami; Osa, Akihiko; Ogawa, Kazuhiko; Horiguchi, Hironori; Inoi, Hiroyuki; et al.

JAEA-Review 2020-056, 51 Pages, 2021/03

JAEA-Review-2020-056.pdf:3.26MB

A group named as "The group for investigation of reasonable safety assurance based on graded approach", which consists of about 10 staffs from Sector of Nuclear Science Research, Safety and Nuclear Security Administration Department, departments for management of nuclear facility, Sector of Nuclear Safety Research and Emergency Preparedness, aims to realize effective graded approach (GA) about management of facilities and regulatory compliance of JAEA. The group started its activities in September, 2019 and has had discussions through 10 meetings and email communications. In the meetings, basic ideas of GA, status of compliance with new regulatory standards at each facility, new inspection system, etc were discussed, while individual investigation at each facility were shared among the members. This report is compiled with expectation that it will help promote rational and effective safety management based on GA by sharing contents of the activity widely inside and outside JAEA.

Evaluation of radiation effects on residents living around the NSRR under external hazards

Motome, Yuiko; Akiyama, Yoshiya; Murao, Hiroyuki

Journal of Nuclear Engineering and Radiation Science, 6(2), p.021115_1 - 021115_11, 2020/04

https://doi.org/10.1115/1.4045075

The nuclear safety research reactor (NSRR) is a research reactor of training research isotopes general atomics -annular core pulse reactor type. The NSRR facility has been utilized for fuel irradiation experiments to study the behaviors of nuclear fuels under reactivity-initiated accident conditions. Under the new regulation standards, which was established after the Fukushima Daiichi accident, research reactors are regulated based on the risk of the facilities. To apply the graded approach, the radiation effects on residents living around the NSRR under the external hazards were evaluated, and the level of the risk of the NSRR facility was investigated. This paper summarizes the result of the evaluation in the case where the safety functions are lost due to a tornado, an earthquake followed by a tsunami. All in all, the risk is confirmed to be relatively low, since the effective dose on the residents is found to be below 5 mSv per event due to the loss of the safety functions.

A Consideration about major business control system for independent administrative institution

Abe, Shinya*; Nakata, Yutaka; Iitsuka, Tomoaki; Yamagishi, Kojiro*

JAERI-Tech 2003-077, 233 Pages, 2003/10

JAERI-Tech-2003-077.pdf:15.07MB

Japanese government is carrying out the administrative reform aiming to promote decentralization of authority, to magnify the field of private sectors, etc. in order to correspond appropriately to matured economy, internationalized market, etc. As one of the reforms, Japanese government decided that JAERI and JNC would unite into an independent administrative agency. The aims of the independent administrative agency institution include realization of effective and transparent system and management. The aim of the present investigation is to be useful for the new agency to develop a major business control system, which manages financial affairs and accounts not only efficiently but also in correspondence with open information to the public and promoting research activities effectively.

Digital interface for instruments-trendo of the CAMAC system

Denshi Tsushin Gakkai-Shi, 61(12), p.1316 - 1325, 1978/00

no abstracts in English

Code development based on the system based code concept

Asayama, Tai

no journal, , 

Following the Strategic Roadmap issued by the Japanese government, various types of fast reactor design will be explored. This requires the development of a set of codes that make the most of new ideas of fast reactor design. This presentation gives an introduction to the activities led by JAEA to establish such codes which is based on the System Based Code concept.