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Journal Articles

Current status and issues for clearance, 5; Concept of restricted use of contaminated rubbles in the Fukushima Daiichi NPS

Shimada, Taro; Miwa, Kazuji; Takeda, Seiji

Nippon Genshiryoku Gakkai-Shi, 61(7), p.531 - 534, 2019/07

Rubbles less than 5 $$mu$$Sv/h of surface dose rate, which are stored outdoor in the Fukushima Daiichi NPS (1F) site, will be recycled and applied in a restricted reuse only within 1F site in the future. However, there is no precedent for establishing the reference values such as dose and/or concentration for reuse or recycling under the existing exposure situation. In this study, we suggested a concept for establishing the reference radioactive concentration of recycling material for the restricted use in the 1F site. In addition, based on the concept, we calculated the reference radiocesium concentrations of the recycling material used for paved roads and the bases of concrete building.

Journal Articles

Journal Articles

Laser cutting technology of thick steel components; Advanced technology developed at the era of decommissioning

Tamura, Koji*; Toyama, Shinichi

Nippon Genshiryoku Gakkai-Shi, 61(5), p.413 - 415, 2019/05

In decommissioning of nuclear reactors, it is necessary to disassemble the nuclear reactor structure. In addition to the conventional cutting method, the laser method has many advantages such as remote controllability and no need for replacement parts such as blades, which can be a powerful choice. Nuclear reactor structure such as a pressure vessel are made of steel materials with a thickness exceeding 100 mm, and the laser method has poor knowledge and experience in cutting such thick steel materials. Therefore, as a result of trial cutting of steel materials under various cutting conditions with the high power fiber laser which is progressively available nowadays, it has been demonstrated that laser cutting is also possible for thick plates such as those used in nuclear reactors, and cutting of thick steel plates. We also developed the cutting technology using remote control using a robot in order to apply it to the decommissioning of thick steel cutting on the spot.

Journal Articles

Let's aim at AESJ without Ethics Committee

Oba, Kyoko

Nippon Genshiryoku Gakkai-Shi, 61(4), p.347 - 348, 2019/04

This article is published in a special feature in commemoration of the 60th anniversary of the Atomic Energy Society of Japan. The article is the contents that "I look back on this, and surveys the future", by chairwoman of Ethics Committee.

Journal Articles

Japan-IAEA nuclear energy management school

Kono, Yuko

Nippon Genshiryoku Gakkai-Shi, 61(2), P. 150, 2019/02

no abstracts in English

Journal Articles

The Prospect of economics of fast reactor cycle

Mukaida, Kyoko; Kato, Atsushi; Kamiya, Masayoshi; Ishii, Katsunori

Nippon Genshiryoku Gakkai-Shi, 61(1), p.40 - 47, 2019/01

Japan Atomic Energy Agency has proceeded on the research and development (R&D) of fast neutron rector fuel cycle with a system which has economic competitiveness in contrast with light water reactor systems as one of development objectives, from the start of its development. This report shows the evaluation results of generation cost of fast reactor fuel cycle in light of additional safety measure cost and social cost, based on the design of fast reactor and related fuel cycle facilities which considered in FaCT phase I.

Journal Articles

Development of safety design guideline of structures, systems and components of Generation-IV Sodium-cooled Fast Reactor

Okano, Yasushi

Nippon Genshiryoku Gakkai-Shi, 60(12), p.764 - 769, 2018/12

JAEA has developed the second safety design guidelines report, "Safety Design Guidelines on Structures, Systems and Components" for Generation-IV SFR system, following the previously published SFR Safety Design Criteria and the first SFR Safety Design Guidelines report and with the reviews by a technical committee under Atomic Energy Society of Japan. This article explains about 14 key points on reactor core system, coolant system, and containment system and also current consistency of international SFR designs to the safety design guidelines.

Journal Articles

The Development status of Generation IV reactor systems, 7; Sodium-cooled Fast Reactor (SFR)

Kamide, Hideki; Ito, Takaya*; Kotake, Shoji*

Nippon Genshiryoku Gakkai-Shi, 60(9), p.562 - 566, 2018/09

Sodium-cooled Fast Reactors (SFRs) have significant characteristics on sustainability as follows, highly effective utilization of Uranium resource, burning of TRU long-life nuclide, e.g., Plutonium, reduction of volume and toxicity of high level radioactive waste of spent fuels. SFRs are one of promising concepts at a step of demonstration phase of development. BN-800 in Russia has already started commercial operation. This is a great step toward the commercialization of SFRs. Russia stated that SFR entered the step of commercial use and next step was demonstration of safety and economy of SFRS by means of operation of BN-1200. Construction of a demo reactor of 600 MWe started in China. In India, operation of PFBR is planned near future and also constructions of 6 units of commercial reactors are also planned. In this report such SFR development plans of oversea countries are summarized including development status and future direction in Japan,

Journal Articles

Cutting-edge studies on nuclear data for continuous and emerging need, 8; Evolution of the nuclear data library JENDL

Iwamoto, Osamu; Shibata, Keiichi; Iwamoto, Nobuyuki; Chiba, Go*

Nippon Genshiryoku Gakkai-Shi, 60(6), p.357 - 361, 2018/06

Nuclear data library consists of the results of related studies on nuclear data. Nuclear data can show worth through utilization of the nuclear data library which is the outcome of the nuclear data study. As the last lecture over 8 serial ones, the Japanese nuclear data library JENDL is explained. Sections of "General purpose file and its history", "recent progress of special purpose file", and "international status of nuclear data library" are introduced and one of "prospect of JENDL and nuclear data study" is shown.

Journal Articles

HOTLAB 2017; 54th Annual Meeting on Hot Laboratories and Remote Handling

Minato, Kazuo

Nippon Genshiryoku Gakkai-Shi, 60(6), P. 365, 2018/06

HOTLAB 2017 was held by the Japan Atomic Energy Agency in cooperation with the Atomic Energy Society of Japan and the International Atomic Energy Agency. This series of meetings has been held every year since 1963 to make information exchange and cooperation on post-irradiation examination and remote handling technologies and safe operation of hot laboratories. 155 engineers and researchers from 21 countries (107 from abroad) participated in the meeting. 51 oral presentations and 29 poster presentations were made. During the meeting a lively discussion was made between engineers being involved in installation of new technology and apparatus in hot cells and researchers aiming at using new ones. There was a great expectation in the construction of a new hot laboratory for analyses of the fuel debris of TEPCO's Fukushima Daiichi Nuclear Power Station. The necessity for facilities and apparatus for sophisticated analyses and measurements on small irradiated samples was emphasized.

Journal Articles

Cutting-edge studies on nuclear data for continuous and emerging need, 7; Challenge to high energy area

Shigyo, Nobuhiro*; Iwase, Hiroshi*; Iwamoto, Yosuke; Sato, Tatsuhiko

Nippon Genshiryoku Gakkai-Shi, 60(5), p.294 - 298, 2018/05

For calculations of neutron productions and radiation damages in nuclear design of Accelerator Driven System (ADS) and exposure doses in radiation cancer therapy, radiation transport simulations with the high-energy nuclear data library evaluated with experimental data play an important role. Experimental data are needed for validation of nuclear reaction models in calculation codes. In this paper, we explain examples of nuclear data measurements in high energy region and the progress of the Particle and Heavy-Ion Transport code System (PHITS) developed in Japan.

Journal Articles

Recent development of nano/micro-scale analytical techniques for nuclear materials, 2; Mechanical strength research using neutron diffraction

Morooka, Satoshi; Suzuki, Hiroshi

Nippon Genshiryoku Gakkai-Shi, 60(5), p.289 - 293, 2018/05

no abstracts in English

Journal Articles

The Development status of Generation IV reactor systems, 2; High temperature gas-cooled reactor (HTGR)

Kunitomi, Kazuhiko; Nishihara, Tetsuo; Yan, X.; Tachibana, Yukio; Shibata, Taiju

Nippon Genshiryoku Gakkai-Shi, 60(4), p.236 - 240, 2018/04

High temperature gas-cooled reactor (HTGR) is a graphite-moderated and helium-gas-cooled thermal-neutron reactor that has excellent safety features and can produce high temperature heat of 950$$^{circ}$$C. It is expected to use for various heat applications as well as for electricity generation to reduce carbon dioxide emission. Japan Atomic Energy Agency (JAEA) has been promoted research and development to demonstrate the HTGR safety features using High temperature engineering test reactor (HTTR) and it's heat application. JAEA are also conducting the action to international deployment of Japanese HTGR technologies in cooperation with industries-government-academia. This paper reports status of the research and development of HTGR and domestic and international collaborations.

Journal Articles

Thermal-hydraulics technological strategy roadmap 2017; An Approach for continuous safety improvement of LWRs

Itoi, Tatsuya*; Iwaki, Chikako*; Onuki, Akira*; Kito, Kazuaki*; Nakamura, Hideo; Nishida, Akemi; Nishi, Yoshihisa*

Nippon Genshiryoku Gakkai-Shi, 60(4), p.221 - 225, 2018/04

no abstracts in English

Journal Articles

Research and development roadmap for reactor physics 2017; Future of reactor physics projected by next generations

Yamamoto, Akio*; Chiba, Go*; Kirimura, Kazuki*; Miki, Yosuke*; Yokoyama, Kenji

Nippon Genshiryoku Gakkai-Shi, 60(4), p.241 - 245, 2018/04

no abstracts in English

Journal Articles

Cutting-edge studies on nuclear data for continuous and emerging need, 6; Processing and validation of nuclear data

Tada, Kenichi; Kosako, Kazuaki*; Yokoyama, Kenji; Konno, Chikara

Nippon Genshiryoku Gakkai-Shi, 60(3), p.168 - 172, 2018/03

The neutronics calculation codes cannot treat the evaluated nuclear data file directly. The nuclear data processing is required to use the nuclear data file in the neutronics calculation codes. The nuclear data processing is not just a converter but also many processes to evaluate the physical values for the neutronics calculation codes. In this paper, we describe the overview of the nuclear data processing and validation of the nuclear data.

Journal Articles

State-of-the-art approach and issue to establish simulation credibility

Nakada, Kotaro*; Kudo, Yoshiro*; Koshizuka, Seiichi*; Tanaka, Masaaki

Nippon Genshiryoku Gakkai-Shi, 60(3), p.173 - 177, 2018/03

The Atomic Energy Society of Japan (AESJ) published "Guideline for Credibility Assessment of Nuclear Simulations 2015" in June, 2016 which specifies the concepts on methodology for the prediction with uncertainty quantification and the quality management based on the concept of verification and validation (V&V) of modeling and simulation. In this report, the outlines of activities in AESJ for publication of the guideline and the expectation for effective implementation of the guideline are described including that of the lectures with major respondents of the questionnaires.

Journal Articles

Report on International Conference; Actinides 2017

Haga, Yoshinori; Yamamura, Tomoo*

Nippon Genshiryoku Gakkai-Shi, 60(3), P. 181, 2018/03

no abstracts in English

Journal Articles

Challenges for enhancing Fukushima environmental resilience, 10; Dose evaluation and risk communication

Saito, Kimiaki; Takahara, Shogo; Uezu, Yasuhiro

Nippon Genshiryoku Gakkai-Shi, 60(2), p.111 - 115, 2018/02

no abstracts in English

Journal Articles

1575 (Records 1-20 displayed on this page)