Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 24

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Sodium-cooled Fast Reactors

Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07

This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.

Journal Articles

Development of an evaluation method for planning of urgent protection strategies in a nuclear emergency using a level 3 probabilistic risk assessment

Kimura, Masanori; Oguri, Tomomi*; Ishikawa, Jun; Munakata, Masahiro

Journal of Nuclear Science and Technology, 58(3), p.278 - 291, 2021/03

 Times Cited Count:2 Percentile:11.8(Nuclear Science & Technology)

The authors developed an evaluation method for planning urgent protection strategies in a nuclear emergency by using a Level 3 Probabilistic Risk Assessment (PRA) code, OSCAAR. For a given accident scenario, the OSCAAR can calculate received doses in the early phase of a nuclear accident and the dose reduction effect of implementing urgent protective actions such as evacuation, sheltering, and iodine thyroid blocking. The authors considered the combination of these urgent protective actions within a precautionary action zone (PAZ) and an urgent protective action planning zone (UPZ) for an accident scenario and then calculated received doses after implementing these protective actions using the OSCAAR. After that, the authors performed sensitivity analysis for protective action models of the OSCAAR and then optimized the protection strategy by reducing doses to below generic criteria of the International Atomic Energy Agency (IAEA). Consequently, the effective urgent protection strategy for the accident scenario could be designed, such as precautionary evacuation within the PAZ, and the combination of evacuation after sheltering, sheltering in concrete building, or in normal housing and thyroid blocking within the UPZ. The developed evaluation method will be very useful in developing effective urgent protection strategies for an accident scenario.

Journal Articles

Development of integrated system for accident consequence evaluation using Level 2 and Level 3 PRA codes

Kimura, Masanori; Ishikawa, Jun; Oguri, Tomomi*; Munakata, Masahiro

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 5 Pages, 2019/05

An integrated system between the THALES2 and the OSCAAR was developed in order to assist in preparing the input file of the OSCAAR. For the result of a state-of-the-art source term analysis with the THALES2, the authors implemented a preliminary analysis using the OSCAAR in order to evaluate the difference in setting of release fraction rates for the radionuclide groups. The effective dose was calculated for some cases by changing of release fraction rates divided into 1h (case 1), 3h (case 2), 5h (case 3), none (case 4) and arbitrary hours (case 5). After that, the ratio of the effective dose for these cases was compared. The result indicates that it was better to set short duration of release stages while the release fraction rates increased sharply. It seems that the case 5 is a better method in order to adapt to various accident scenarios. The method shows that it is useful for reducing the uncertainty in a Level 3 PRA analysis.

Journal Articles

Bipartite magnetic parent phases in the iron oxypnictide superconductor

Hiraishi, Masatoshi*; Iimura, Soshi*; Kojima, Kenji*; Yamaura, Junichi*; Hiraka, Haruhiro*; Ikeda, Kazutaka*; Miao, P.*; Ishikawa, Yoshihisa*; Torii, Shuki*; Miyazaki, Masanori*; et al.

Nature Physics, 10(4), p.300 - 303, 2014/04

 Times Cited Count:103 Percentile:95.39(Physics, Multidisciplinary)

Journal Articles

Assessment of doses from external exposure in contaminated areas resulting from the Fukushima Daiichi Nuclear Power Plant accident

Takahara, Shogo; Kimura, Masanori; Kinase, Sakae; Ishikawa, Jun; Suyama, Kenya; Hosoyamada, Ryuji; Homma, Toshimitsu

Progress in Nuclear Science and Technology (Internet), 3, p.25 - 29, 2012/10

Dose assessment is one of the important issues to make decisions in contaminated areas resulting from the Fukushima Daiichi Nuclear Power Plant accident. The doses to inhabitants of contaminated areas should be assessed prospectively and retrospectively taking into account the impact from various exposure pathways. The external exposure from deposited radioactive materials of short-lived and long-lived is one of the most important pathways. In the present study, the radionuclide compositions have been evaluated by source term analysis taking into account 54 radionuclides. This analysis consists in evaluating the inventory and the fraction of the radionuclides that were released into the atmosphere. On the assumption that dose rate may be decreased due to the radioactive decay as well as weathering effects, we have assessed the dose for future and past at the contaminated areas. The assessed values are almost consistent with the measured ones during the first month.

JAEA Reports

Conceptual design of multipurpose compact research reactor; Annual report FY2010 (Joint research)

Imaizumi, Tomomi; Miyauchi, Masaru; Ito, Masayasu; Watahiki, Shunsuke; Nagata, Hiroshi; Hanakawa, Hiroki; Naka, Michihiro; Kawamata, Kazuo; Yamaura, Takayuki; Ide, Hiroshi; et al.

JAEA-Technology 2011-031, 123 Pages, 2012/01

JAEA-Technology-2011-031.pdf:16.08MB

The number of research reactors in the world is decreasing because of their aging. However, the planning to introduce the nuclear power plants is increasing in Asian countries. In these Asian countries, the key issue is the human resource development for operation and management of nuclear power plants after constructed them, and also the necessity of research reactor, which is used for lifetime extension of LWRs, progress of the science and technology, expansion of industry use, human resources training and so on, is increasing. From above backgrounds, the Neutron Irradiation and Testing Reactor Center began to discuss basic concept of a multipurpose low-power research reactor for education and training, etc. This design study is expected to contribute not only to design tool improvement and human resources development in the Neutron Irradiation and Testing Reactor Center but also to maintain and upgrade the technology on research reactors in nuclear power-related companies. This report treats the activities of the working group from July 2010 to June 2011 on the multipurpose low-power research reactor in the Neutron Irradiation and Testing Reactor Center and nuclear power-related companies.

JAEA Reports

Survey on current status of international organizations and foreign countries for emergency preparedness and response and consider technical issues on guideline for nuclear emergency preparedness

Kimura, Masanori; Sato, Sohei; Ishikawa, Jun; Homma, Toshimitsu

JAEA-Review 2010-011, 147 Pages, 2010/06

JAEA-Review-2010-011.pdf:1.66MB

The review report describes survey results of nuclear emergency preparedness and response in international organizations and foreign countries, and consideration results of technical issues on the "Guideline for Nuclear Emergency Preparedness" issued by the NSC. In order to respond to nuclear emergency more effectively, the guideline should show the basic concept of emergency preparedness and response for the period between the beginning of the nuclear accident and the termination of early protective measurements. In order to introduce these new concepts to the guideline, all necessary issues should be arranged and considered in reference to the recent trend for the concept of nuclear emergency preparedness and response in international organizations and foreign countries.

Journal Articles

Plasma physics and radiation hydrodynamics in developing an extreme ultraviolet light source for lithography

Nishihara, Katsunobu*; Sunahara, Atsushi*; Sasaki, Akira; Nunami, Masanori*; Tanuma, Hajime*; Fujioka, Shinsuke*; Shimada, Yoshinori*; Fujima, Kazumi*; Furukawa, Hiroyuki*; Kato, Takako*; et al.

Physics of Plasmas, 15(5), p.056708_1 - 056708_11, 2008/00

 Times Cited Count:122 Percentile:97.47(Physics, Fluids & Plasmas)

Journal Articles

Technical considerations for emergency preparedness with a probabilistic accident consequence assessment model

Homma, Toshimitsu; Kimura, Masanori; Matsubara, Takeshi*; Ishikawa, Jun

Proceedings of 9th International Probabilistic Safety Assessment and Management Conference (PSAM-9) (CD-ROM), 6 Pages, 2008/00

Journal Articles

An Application of accident consequence assessment models to off-site emergency planning

Kimura, Masanori; Matsubara, Takeshi; Ishikawa, Jun; Homma, Toshimitsu

Proceedings of International Symposium on Environmental Modeling and Radioecology, p.348 - 351, 2007/03

no abstracts in English

JAEA Reports

None

Ishikawa, Hirohisa; Sakamaki, Masanori*; Takeda, Seietsu; Yui, Mikazu; Mckinley, I. G.*

JNC TN1400 2004-015, 119 Pages, 2005/03

JNC-TN1400-2004-015.pdf:46.52MB

no abstracts in English

JAEA Reports

Feasibility Study on Commercialization of Fast Breeder Reactor Cycle Systems Interim Report of Phase II; Technical Study Report for Reactor Plant Systems

Konomura, Mamoru; Ogawa, Takashi; Okano, Yasushi; Yamaguchi, Hiroyuki; Murakami, Tsutomu; Takaki, Naoyuki; Nishiguchi, Youhei; Sugino, Kazuteru; Naganuma, Masayuki; Hishida, Masahiko; et al.

JNC TN9400 2004-035, 2071 Pages, 2004/06

JNC-TN9400-2004-035.pdf:76.42MB

The attractive concepts for Sodium-, lead-bismuth-, helium- and water-cooled FBRs have been created through using typical plant features and employing advanced technologies. Efforts on evaluating technological prospects of feasibility have been paid for these concepts. Also, it was comfirmed if these concepts satisfy design requierments of capability and performance presumed in the feasibilty study on commertialization of Fast Breeder Reactor Systems. As results, it was concluded that the selection of sodium-cooled reactor was most rational for practical use of FBR technologies in 2015.

JAEA Reports

Research and development on reduced-moderation light water reactor with passive safety features (Contract research)

Iwamura, Takamichi; Okubo, Tsutomu; Akie, Hiroshi; Kugo, Teruhiko; Yonomoto, Taisuke; Kureta, Masatoshi; Ishikawa, Nobuyuki; Nagaya, Yasunobu; Araya, Fumimasa; Okajima, Shigeaki; et al.

JAERI-Research 2004-008, 383 Pages, 2004/06

JAERI-Research-2004-008.pdf:21.49MB

The present report contains the achievement of "Research and Development on Reduced-Moderation Light Water Reactor with Passive Safety Features", which was performed by Japan Atomic Energy Research Institute (JAERI), Hitachi Ltd., Japan Atomic Power Company and Tokyo Institute of Technology in FY2000-2002 as the innovative and viable nuclear energy technology (IVNET) development project operated by the Institute of Applied Energy (IAE). In the present project, the reduced-moderation water reactor (RMWR) has been developed to ensure sustainable energy supply and to solve the recent problems of nuclear power and nuclear fuel cycle, such as economical competitiveness, effective use of plutonium and reduction of spent fuel storage. The RMWR can attain the favorable characteristics such as high burnup, long operation cycle, multiple recycling of plutonium (Pu) and effective utilization of uranium resources based on accumulated LWR technologies.

Journal Articles

X-ray diffraction measurements for expanded fluid Se using synchrotron radiation up to the dense vapor region

Inui, Masanori*; Hong, X.*; Matsusaka, Tetsuya*; Ishikawa, Daisuke*; Kazi, M. H.*; Tamura, Kozaburo*; Funakoshi, Kenichi*; Utsumi, Wataru

Journal of Non-Crystalline Solids, 312-314, p.274 - 278, 2002/10

 Times Cited Count:2 Percentile:30.86(Materials Science, Ceramics)

no abstracts in English

Journal Articles

ITER engineering design

Shimomura, Yasuo; Tsunematsu, Toshihide; Yamamoto, Shin; Maruyama, So; Mizoguchi, Tadanori*; Takahashi, Yoshikazu; Yoshida, Kiyoshi; Kitamura, Kazunori*; Ioki, Kimihiro*; Inoue, Takashi; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 78(Suppl.), 224 Pages, 2002/01

no abstracts in English

JAEA Reports

Investigation program in borehole MIU-2 for the Mizunami Underground Research Laboratory project in the Shobasama site

Ishikawa, Kiyoshi*; Mezaki, Yoshihiko*; Suzuki, Hideo*; Kai, Masanori*; Watanabe, Hajime*; Fujimori, Seiji*; Ishikawa, Junichi*

JNC TJ7420 99-016, 878 Pages, 1999/06

JNC-TJ7420-99-016.pdf:40.87MB

no abstracts in English

JAEA Reports

The Study on transition of faulting area

Yoneda, Shigeo*; Ishikawa, Masanori*

PNC TJ7308 94-005, 82 Pages, 1994/03

PNC-TJ7308-94-005.pdf:6.02MB

no abstracts in English

Oral presentation

Study on stable iodine administration using a PSA methodology

Homma, Toshimitsu; Kimura, Masanori; Matsubara, Takeshi; Ishikawa, Jun

no journal, , 

no abstracts in English

Oral presentation

Consideration of off-site emergency planning and response using probabilistic accident consequence assessment models

Kimura, Masanori; Ishikawa, Jun; Homma, Toshimitsu

no journal, , 

no abstracts in English

Oral presentation

Risk-informed evaluation of off-site response planning for nuclear emergencies

Homma, Toshimitsu; Kimura, Masanori; Takahara, Shogo; Ishikawa, Jun

no journal, , 

It is recognized that good preparedness in advance of an emergency can substantially improve the emergency response to a nuclear or radiological accident. In particular, it is very important to provide technical guidance for the development of protective action strategies based upon a comprehensive analysis which takes into account the full range of postulated events. Probabilistic accident consequence assessment models can be very useful for providing a quantitative basis for discussing the effective emergency preparedness for appropriate protective action strategies such as sheltering, evacuation, and stable iodine prophylaxis. This paper presents the methodology and results of the risk-informed evaluation of off-site emergency planning using the level 3 PSA code, called OSCAAR developed at JAEA. Calculations of the off-site consequence have been made of postulated core damage accidents with source terms derived from a generic level 2 PSA of the reference plant.

24 (Records 1-20 displayed on this page)