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Journal Articles

How the Cesium-bearing microparticles were generated?; Inference of an interdiscipinary researcher

Hidaka, Akihide

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 63(9), p.679 - 680, 2021/09

no abstracts in English

Journal Articles

Concepts and basic designs of various nuclear fuels, 5; Fuels for high temperature gas-cooled reactor and molten salt reactor

Ueta, Shohei; Sasaki, Koei; Arita, Yuji*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 63(8), p.615 - 620, 2021/08

no abstracts in English

Journal Articles

Growing need for humanities and social science studies in uranium waste disposal

Yasuda, Hiroshi*; Fumoto, Hiromichi*; Saito, Tatsuo

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 63(8), p.610 - 614, 2021/08

Regarding the handling of uranium bearing waste, which is contaminated with uranium, which is a naturally occurring radionuclide, and its descendant nuclides, in recent years, the Japan Nuclear Regulatory Commission, etc. have been carefully and actively deliberated based on the knowledge of natural science and safety engineering. It was carried out, and as of March 2021, a certain policy has been shown. On the other hand, when disposing of uranium waste, which may cause dose exposure to future generations, the authors consider not only the science and engineering perspectives that have been conducted so far, but also the humanities and social science perspectives. We have been discussing with experts in related fields, thinking that it is necessary. In this report, we will introduce the background that brought about such an idea and the direction of future discussions.

Journal Articles

The Progress of R&D for decommissioning technologies; Achievements and challenges

Noda, Koichi

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 63(7), p.536 - 540, 2021/07

no abstracts in English

Journal Articles

Thermal-hydraulics to risk assessment; Roles of thermal-hydraulics simulation to risk assessment

Maruyama, Yu; Yoshida, Kazuo

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 63(7), p.517 - 522, 2021/07

no abstracts in English

Journal Articles

Concepts and basic designs of various nuclear fuels, 4; Metallic fuels for fast reactors and nitride fuels for ADS

Ogata, Takanari*; Takano, Masahide

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 63(7), p.541 - 546, 2021/07

This is a commentary on metallic fuels for fast reactors and nitride fuels for minor actinide transmutation in accelerator driven system, as the 4th article of serial lecture on Journal of the Atomic Energy Society of Japan; Concepts and basic designs of various nuclear fuels.

Journal Articles

Overview of the technical review group activity related to shielding experiment in OECD/NEA

Tsuda, Shuichi

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 63(5), p.415 - 419, 2021/05

This article reports the recent activity on the integral shielding experimental database in Nuclear Energy Agency (NEA) in Organisation for Economic Co-operation and Development (OECD). The author had been working as a secretary in the division of Nuclear Science in NEA for three years by September 2020. The Division of Nuclear Science has been playing an important role to provide a place for exchanging information about nuclear physics and nuclear data, recently about fuels and materials as well, and to develop various experimental databases. Japanese participants have historically contributed to the integral experimental databases of criticality safety, nuclear physics, and shielding. Due to expansion of world-wide shutdowns of nuclear experimental facilities, importance of data preservation has been increasing, and further contributions from Japanese community are expected. This paper will report the OECD/NEA integral shielding experimental database and the recent activity of technical review group that is indispensable for preparation of database with high reliability.

Journal Articles

Overview of OECD/NEA and contribution of Japan, 5; Nuclear Science Committee and the Data Bank

Tsuda, Shuichi; Suyama, Kenya*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 63(3), p.278 - 282, 2021/03

Series of articles have been posted to Journal of the Atomic Energy Society of Japan (ATOMO$$Sigma$$) by Japanese secretaries working in Nuclear Energy Agency (NEA) in Organisation for Economic Co-operation and Development (OECD) to share the recent information. The Division of Nuclear Science has been playing an important role to provide a place for exchanging information about nuclear physics and nuclear data, recently about fuels and materials as well, and the author had been working in the Division as a secretariat for three years since September 2017. The Data bank is in charge of management and distribution of databases developed in NEA, and has been strengthening the user support system and cooperation with other NEA committees. This paper will report the recent activities related to Nuclear Science and the Data bank, and hopefully also provide information for further deepening relations between NEA and the Japanese participants by introducing their contributions.

Journal Articles

Issues and recommendations about application of graded approach to research reactors

Yonomoto, Taisuke; Mineo, Hideaki; Murayama, Yoji; Hohara, Shinya*; Nakajima, Ken*; Nakatsuka, Toru; Uesaka, Mitsuru*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 63(1), p.73 - 77, 2021/01

no abstracts in English

Journal Articles

Worldwide status and issue of nuclear safety against pandemic

Kobayashi, Tetsuro*; Takata, Takashi; Narumiya, Yoshiyuki*; Iida, Susumu*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 63(1), p.50 - 54, 2021/01

Since December 2019, the new coronavirus infectious disease COVID-19, which has occurred mainly in Wuhan City, Hubei Province, China, rapidly spread as a pandemic (a global pandemic of infectious diseases). And thus it affected financial and social issues extremely. In this paper, the current status and issues of non-medical measures in Japan and overseas are explained with regard to the safety of nuclear facilities against pandemics.

Journal Articles

Development of Short-Term Emergency Assessment system of Marine Environmental Radioactivity

Kobayashi, Takuya; Kawamura, Hideyuki; Kamidaira, Yuki

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 62(11), p.635 - 639, 2020/11

It is important to predict the dispersion of radioactive materials released into the ocean due to nuclear accidents in the surrounding ocean of the east Asian countries. The Japan Atomic Energy Agency developed a Short-Term Emergency Assessment system of Marine Environmental Radioactivity (STEAMER) based on an oceanic dispersion model. STEAMER quickly predicts the oceanic dispersion of radioactive materials in the surrounding ocean of the east Asian countries using the online prediction data of oceanic condition. We validated the predictability of the oceanic dispersion and demonstrated the improvement of the predictability using an ensemble prediction method. Moreover, we developed a high resolution model in the coastal region using a Regional Ocean Modeling System (ROMS).

Journal Articles

Frontline of R&D for decommissioning and waste disposal, 1; R&D for processing and disposal of low-level radioactive waste and closure of uranium mine

Tsuji, Tomoyuki; Sugitsue, Noritake; Sato, Fuminori; Matsushima, Ryotatsu; Kataoka, Shoji; Okada, Shota; Sasaki, Toshiki; Inoue, Junya

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 62(11), p.658 - 663, 2020/11

no abstracts in English

Journal Articles

Development and release of fuel performance code FEMAXI-8

Udagawa, Yutaka

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 62(10), p.555 - 559, 2020/10

no abstracts in English

Journal Articles

Research and development activities of JAEA for HTGR system realization

Mineo, Hideaki; Nishihara, Tetsuo; Ohashi, Hirofumi; Goto, Minoru; Sato, Hiroyuki; Takegami, Hiroaki

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 62(9), p.504 - 508, 2020/09

High-Temperature Gas-cooled Reactor (HTGR) is one of thermal neutron reactor-type that employs helium gas coolant and graphite moderator. It has excellent inherent safety and can supply high-temperature heat which can be used not only for electric power generation but also for a wide range of application such as hydrogen production. Therefore, HTGR is expected to be an effective technology for reducing greenhouse gases in Japan as well as overseas. In this paper, we will introduce the forefront of technological development that JAEA is working toward the realization of an HTGR system consisting of a high temperature gas reactor and heat utilization facilities such as gas-turbine power generation and hydrogen production.

Journal Articles

Introduction to nuclear security, 3; Nuclear material detection technique for nuclear security

Takahashi, Yoshiyuki*; Koizumi, Mitsuo

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 62(8), p.452 - 456, 2020/08

no abstracts in English

Journal Articles

Now is the time of fast reactor

Negishi, Hitoshi; Kamide, Hideki; Maeda, Seiichiro; Nakamura, Hirofumi; Abe, Tomoyuki

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 62(8), p.438 - 441, 2020/08

Prototype Fast Breeder Reactor, Monju, was under decommission since April, 2018. It is the first time for Japan to make a sodium cooled reactor into decommission. It is significant work and will take 30 years. The Monju has provided wide spectrum and huge amount of findings and knowledge, e.g., design, R&D, manufacturing, construction, and operation up to 40% of full power over 50 years of development history. It is significant to utilize such findings and knowledge for the development and commercialization of a fast rector in Japan.

Journal Articles

For better understanding of PRA; Guidance for better usage and application of PRA, 3; Consideration of external hazard in PRA

Takata, Takashi*; Yamano, Hidemasa; Narumiya, Yoshiyuki*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 62(8), p.448 - 451, 2020/08

This report describes risk analysis applicable to selection and evaluation of external hazards in risk assessment. Volcanic ash hazard evaluation is shown as one of hazard evaluations. The objective of the risk assessment is to secure and improve the safety of nuclear installation. This report also describes discussion on the process of response informed based on risk evaluation against external hazards.

Journal Articles

For better understanding of PRA; Guidance for better usage and application of PRA, 1; Technical issues in probabilistic risk assessment

Maruyama, Yu; Kita, Toshinobu*; Kuramoto, Takahiro*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 62(6), p.328 - 333, 2020/06

no abstracts in English

1621 (Records 1-20 displayed on this page)