Japanese Evaluated Nuclear Data Library version 5; JENDL-5

Iwamoto, Osamu; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Nakayama, Shinsuke; Abe, Yutaka*; Tsubakihara, Kosuke*; Okumura, Shin*; Ishizuka, Chikako*; Yoshida, Tadashi*; et al.

Journal of Nuclear Science and Technology, 60(1), p.1 - 60, 2023/01

https://doi.org/10.1080/00223131.2022.2141903

Focusing and spin polarization of atomic hydrogen beam

Nagaya, Yuki*; Nakatsu, Hiroki*; Ogura, Shohei*; Shimazaki, Kota*; Ueta, Hirokazu; Takeyasu, Kotaro*; Fukutani, Katsuyuki

Journal of Chemical Physics, 155(19), p.194201_1 - 194201_6, 2021/11

https://doi.org/10.1063/5.0068251

Development of the Unified Cross-section Set ADJ2017

Yokoyama, Kenji; Sugino, Kazuteru; Ishikawa, Makoto; Maruyama, Shuhei; Nagaya, Yasunobu; Numata, Kazuyuki*; Jin, Tomoyuki*

JAEA-Research 2018-011, 556 Pages, 2019/03

JAEA-Research-2018-011.pdf:19.53MB
JAEA-Research-2018-011-appendix1(DVD-ROM).zip:433.07MB
JAEA-Research-2018-011-appendix2(DVD-ROM).zip:580.12MB
JAEA-Research-2018-011-appendix3(DVD-ROM).zip:9.17MB

We have developed a new unified cross-section set ADJ2017, which is an improved version of the unified cross-section set ADJ2010 for fast reactors. The unified cross-section set is used for reflecting information of C/E values (analysis / experiment values) obtained by integral experiment analyses; the values are stored in the standard database for FBR core design via the cross-section adjustment methodology, which integrates with the information such as uncertainty (covariance) of nuclear data, uncertainty of integral experiment / analysis, sensitivity of integral experiment with respect to nuclear data. The ADJ2017 is based on Japan's latest nuclear data library JENDL-4.0 as in the previous version of ADJ2010, and it incorporates more information on integral experimental data sets related to minor actinides (MAs) and degraded plutonium (Pu). In the creation of ADJ2010, a total of 643 integral experimental data sets were analyzed and evaluated, and 488 of the integral experimental data sets were finally selected to be used for the cross-section adjustment. In contrast, we have evaluated a total of 719 data sets, and eventually adopted 620 integral experimental data sets to create ADJ2017. ADJ2017 shows almost the same performance as ADJ2010 for the main neutronic characteristics of conventional sodium-cooled MOX-fuel fast reactors. In addition, for the neutronic characteristics related to MA and degraded Pu, ADJ2017 improves the C/E values of the integral experimental data sets, and reduces the uncertainty induced by the nuclear data. ADJ2017 is expected to be widely used in the analysis and design research of fast reactors. Moreover, it is expected that the integral experimental data sets used for ADJ2017 can be utilized as a standard database of FBR core design.

Enhancement of the functions of the Japan Atomic Energy Agency Library's Fukushima Nuclear Accident Archive using a novel data flagging system that improves the utilization of numerical data on the internet

Ikeda, Kiyoshi; Gonda, Mayuki; Nagaya, Shun; Hayakawa, Misa; Kunii, Katsuhiko; Mineo, Yukinobu; Yonezawa, Minoru; Itabashi, Keizo

Proceedings of 16th International Conference on Grey Literature (GL-16), p.139 - 145, 2015/03

The Japan Atomic Energy Agency (JAEA) Library has collected Internet information related the Fukushima Accident. We previously reported the development of the Fukushima Accident Archive using the DSpace in 15th International Conference on Grey Literature. We have encountered a new challenging issue grey literature. In many cases, Internet information contains valuable numerical data. However, it is difficult to identify the existence of numerical data in the Internet sites because numerical data is not often organized in a systematic manner on the web sites. We considered such method as to identify numerical data and attempted to introduce "data flagging" system, which was previously used in the International Atomic Energy Agency's International Nuclear Information System (INIS). In this presentation, we will introduce our "data flagging" system for numerical data on the Internet and how we apply the system to our Fukushima Accident Archive.

Study to improve recriticality evaluation methodology after severe accident (Joint research)

Kugo, Teruhiko; Ishikawa, Makoto; Nagaya, Yasunobu; Yokoyama, Kenji; Fukaya, Yuji; Maruyama, Hiromi*; Ishii, Yoshihiko*; Fujimura, Koji*; Kondo, Takao*; Minato, Hirokazu*; et al.

JAEA-Research 2013-046, 53 Pages, 2014/03

JAEA-Research-2013-046.pdf:4.42MB

The present report summarizes the results of a 2-year cooperative study between JAEA and Hitachi-GE in order to contribute to the settlement of the Fukushima-Daiichi Nuclear Power Plants which suffered from the severe accident on March 2011. In the present study, the possible scenarios to reach the recriticality events in Fukushima-Daiichi were investigated first. Then, the analytical methodology to evaluate the time-dependent recriticality events has been developed by modelling the reactivity insertion rate and the possible feedback according to the recriticality scenarios identified in the first step. The methodology developed here has been equipped as a transient simulation tool, PORCAS, which is operated on a multi-purpose platform for reactor analysis, MARBLE. Finally, the radiation exposure rates by the postulated recriticality events in Fukushima-Daiichi were approximately evaluated to estimate the impact to the public environment.

Contribution to the improvement of dissemination of grey literature; JAEA Library's efforts for collecting, organizing and disseminating information on nuclear accidents

Ikeda, Kiyoshi; Oshima, Takeshi; Gonda, Mayuki; Nagaya, Shun; Hayakawa, Misa; Mineo, Yukinobu; Yonezawa, Minoru; Itabashi, Keizo

The Grey Journal; An International Journal on Grey Literature, 10(1), p.7 - 13, 2014/00

In March 2011, the Fukushima Daiichi Nuclear Power Station Accident occurred in Japan. After the accident, parts of information on the accident has been distributed as grey literature and they cause some issues in terms of permanent accessibility to the information. This paper introduces the activity of the Japan Atomic Energy Agency Library as an example of efforts to improve access of Internet information using the DSpace. Consequently, we contributed to the improvement of the dissemination of grey literature at the following three points; (1)to ensure permanent access to Internet information by cooperating with the National Diet Library's Web archiving project, (2) to develop standardized metadata schema and classification system, (3)to develop prototype system using DSpace and compile about 36,000 metadata.

Collection of conference proceedings and improving access to the full text of proceedings

Hayakawa, Misa; Nagaya, Shun; Gonda, Mayuki; Fukazawa, Takeyasu; Yonezawa, Minoru; Itabashi, Keizo

Proceedings of 14th International Conference on Grey Literature (GL-14), p.143 - 148, 2012/11

http://hdl.handle.net/10068/700175

In this presentation, we would like to introduce the present status of the collection of conference proceedings (proceedings) in the JAEA Library and the improvement of access to the full text of proceedings. Conference Proceedings have been published mainly in conventional book form from. But, in recent years, their publication form has been changing. Nowadays, they have been publishing in the form of a CD-ROM, or Internet. They become typical gray literature, because many of them are not commercially available. Accessibility to the full text of conference proceedings on the Internet seems improved. But, conference proceedings on the Internet have a specific problem of information on the Internet. For example, there is a possibility that access URL is changed. As a good practice for the improvement of accessibility to the full text of proceedings, we would like to introduce the case of the JAEA library. So, we would like to examine the problems of the availability of proceedings as a whole.

INIS-based Japanese literature materials of bibliographic tools for human resource development

Kunii, Katsuhiko; Gonda, Mayuki; Ikeda, Kiyoshi; Nagaya, Shun; Itabashi, Keizo; Nakajima, Hidemitsu; Mineo, Yukinobu

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 8 Pages, 2011/12

The Library of the Japan Atomic Energy Agency (JAEA) has developed two Japanese literature materials of bibliographic tools based on the International Nuclear Information System (INIS) of the IAEA which contains over 3.3 million records of 127 countries and 24 international organizations. These materials have been elaborated by appropriately designating Japanese terminology of nuclear field corresponding with English terminology or vice versa. One is "Transliterated Japanese journal title list" and the other is "INIS Thesaurus in Japanese". While the former is served as a reference that enables users to access articles of Japanese journals better matching their needs, the latter is served as a dictionary to bridge the gap on nuclear field terminologies between over 30,000 English terms and Japanese terms which correspond with those in a semantic manner. The application of those materials to the INIS's full text collection over 280,000 of technical reports, proceedings etc. as an archive is helpful for enhancement of human resource development. The authors describe the effectiveness of those INIS-based materials with bibliographic references of Fukushima Daiichi NPS accident.

Development of the next generation reactor analysis code system, MARBLE

Yokoyama, Kenji; Tatsumi, Masahiro*; Hirai, Yasushi*; Hyodo, Hideaki*; Numata, Kazuyuki*; Iwai, Takehiko*; Jin, Tomoyuki*; Hazama, Taira; Nagaya, Yasunobu; Chiba, Go; et al.

JAEA-Data/Code 2010-030, 148 Pages, 2011/03

JAEA-Data-Code-2010-030.pdf:3.23MB

A next generation reactor analysis code system, MARBLE, has been developed. MARBLE is a successor of the fast reactor neutronics analysis code systems, JOINT-FR and SAGEP-FR (conventional system), which were developed for so-called JUPITER standard analysis methods. MARBLE has the equivalent analysis capability to the conventional system. On the other hand, burnup analysis functionality for power reactors as improved compared with the conventional system. In the development of MARBLE, the object oriented technology was adopted. As a result, MARBLE became an assembly of components for building an analysis code (i.e. framework) but not an independent analysis code system which simply receives input and returns output. Furthermore, MARBLE provides some pre-built analysis code systems such as the fast reactor neutronics analysis code system, SCHEME, which corresponds to the conventional code and the fast reactor burnup analysis code system, ORPHEUS.

Necessity and prospect for development of radiation behavior simulation code system made in Japan

Sakamoto, Yukio; Chiba, Satoshi; Nagaya, Yasunobu

Nihon Genshiryoku Gakkai-Shi ATOMO, 51(12), p.875 - 879, 2009/12

http://ci.nii.ac.jp/naid/10025445557

The MCNP/MCNPX codes are widely used for nuclear analyses and critical safety evaluations in nuclear facilities, shielding calculations of neutrons and photons, and behavior analyses and shielding calculations of high energy radiation in accelerators facilities. In this April, Radiation Safety Information Computational Center (RSICC) of Oak Ridge National Laboratory (ORNL) in USA sent the message that the new distributions of these codes should be stopped for the time being to Research Organization for Information Science & Technology (RIST) which can distribute codes registered by RSICC in Japan. The persons concerned were shocked by the news. These codes are used for design calculations and experimental analyses, and incorporated in newly developing codes. In this paper, the present status of these code usage and code development incorporated by these is reviewed. Fortunately codes and data set, the general-purpose neutron and photon transport Monte Carlo code MVP for reactor nuclear analyses, particle and heavy ion transport code system PHITS for behavior analyses of various radiation with wide range energy and JENDL-4 for nuclear data, are developing and preparing steadily in Japan.