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Yamamoto, Tomohiko; Kato, Atsushi; Chikazawa, Yoshitaka; Negishi, Kazuo
Journal of Disaster Research, 7(5), p.645 - 655, 2012/10
Japan Sodium-cooled Fast Reactor (JSFR) adopts a new concept of a containment vessel called steel plate reinforced concrete containment vessel (SCCV). The SCCV is considered to be effective to shorten construction period thanks for elimination of rebar work at a site compared with applying a reinforced concrete CV. An SFR CV is lower pressure environment than the LWR CV, although environmental temperature of the SFR is much higher than that of LWR in the accident of coolant leakage. Therefore it is important to investigate its characteristics under high temperature to adopt the SC structure to the JSFR CV because the CV shall keep their containment function in the accidents to be assumed in design. This paper describes the construction of design evaluation method from design, experimental and analytical point of view.
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
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.
Eto, Masao*; Kamishima, Yoshio*; Okamura, Shigeki*; Watanabe, Osamu*; Oyama, Kazuhiro*; Negishi, Kazuo; Kotake, Shoji*; Sakamoto, Yoshihiko; Kamide, Hideki
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009) (CD-ROM), 10 Pages, 2012/00
In the JSFR design, the diameter of the Reactor Vessel (RV) shall be minimized and the reactor internal structures shall be simplified for reduction in construction cost. The reduction in the RV diameter is achieved by adopting an advanced refueling system and the hot RV with high temperature wall. The flow velocity in the reactor upper plenum increases because the diameter of the RV is decreased. As the result, the coolant flow field in reactor upper plenum is severe. The optimization of the coolant flow field in the reactor upper plenum was carried out for prevention the cover gas entrainment and the vortex cavitations at the hot leg intake. In addition, structural integrities for seismic loadings and thermal loadings were evaluated because the design seismic loading was highly increased and the vessel wall is directly exposed to the thermal transients of the upper plenum. This paper describes the characteristics and the results of the design study of the reactor system.
Okamura, Shigeki*; Eto, Masao*; Kamishima, Yoshio*; Negishi, Kazuo; Sakamoto, Yoshihiko; Kitamura, Seiji; Kotake, Shoji*
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009) (CD-ROM), 10 Pages, 2012/00
This paper describes the seismic design of JSFR, which includes the seismic condition, the seismic isolation system and the seismic evaluation of primary component. JSFR employs a seismic isolation system to mitigate the earthquake force. The design seismic loading is made more severe than ever since Niigata-ken Chuetsu-oki Earthquake in 2007. The earthquake force loaded on the primary components has to be mitigated more than that of the previous seismic isolation system. We examined the advanced seismic isolation system by optimizing the performance of the previous seismic isolation system considering the natural frequency of the primary components. The advanced seismic isolation system for SFR was adopted laminated rubber bearings which are thicker than that of the previous, as well as oil dampers. The seismic evaluation of nuclear reactor components under applying the advanced seismic isolation system was performed; the performance of the system was confirmed.
Kato, Atsushi; Negishi, Kazuo; Yamamoto, Tomohiko; Akiyama, Yo*; Hara, Hiroyuki*; Iwasaki, Mikinori*
Transactions of 21st International Conference on Structural Mechanics in Reactor Technology (SMiRT-21) (CD-ROM), 8 Pages, 2011/11
Japan Sodium-cooled Fast Reactor (JSFR) adopts a new concept of a containment vessel called steel plate reinforced concrete containment vessel (SCCV). The SCCV is considered to be effective to shorten construction period thanks for elimination of rebar work at a site compared with applying the reinforced concrete CV. Other than this advantage, the SCCV achieves high quality in building structure, since steel structure parts can be fabricated at a factory prior to the site construction. Although the SC structure has been used for the buildings of LWR etc, it is important to investigate its characteristics under high temperature to adopt the SC structure to the JSFR CV. This paper mainly describes the design study and experiments to investigate potential characteristics of the SC structure under hypothetical sodium combustion in the CV.
Kawasaki, Nobuchika; Okamura, Shigeki*; Sawa, Naoki*; Sakamoto, Yoshihiko; Negishi, Kazuo
Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 7 Pages, 2011/10
Japan Sodium-Cooled Fast Reactor adopts an compacted hot reactor vessel concept. From the point of structural designs to ensure both seismic design and elevated temperature design is important. In this study, based on a common conservative seismic loading condition considered with the Niigata-ken Chuetsu-oki Earthquake, seismic evaluations were carried out, the thicknesses of reactor vessels of 750 MWe and 500 MWe output plants were determined. For both plants 50 mm was selected as the thickness, and ensured buckling evaluation margins were more than 2.4. From the point of seismic design, the difference of plant output was negligible. With the condition of 50 mm thickness of reactor vessel, thermal integrities were evaluated. For three plant start-up conditions which were 2.2, 3.2, and 4.3 days, thermal ratcheting and creep-fatigue damage were evaluated. As a result plant start-up period needed more than 3.2 days for both 750 MWe and 500 MWe output plants. Caused thermal stress were the nearly same for both plants, therefore from the point of thermal design, the difference of plant output was negligible.
Kato, Atsushi; Negishi, Kazuo; Akiyama, Yo*; Hara, Hiroyuki*
Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 10 Pages, 2011/10
Japan Sodium-Cooled Fast Reactor (JSFR) adopts new concept of containment vessel called steel plate reinforced concrete containment vessel (SCCV). The SCCV is considered to be effective to shorten construction schedule due to elimination of rebar work at a site and so on. Although the SC structure has been used for the buildings of LWR etc, it is important to investigate its characteristics under temperature load to adopt as the containment vessel. This paper describes experimental investigations of characteristics of the SC structure under 700 centigrade(C) at the surface steel plate which is decided assuming hypothetical sodium combustion in the containment vessel to study the potential strength of the SC structure.
Kato, Atsushi; Negishi, Kazuo; Akiyama, Yo*; Kubo, Shigenobu*
Dai-15-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.231 - 232, 2010/06
Reduction of plant construction cost is one of the most important issues for commercialization of fast reactors. From this point of view, an innovative containment vessel adopting steel plate reinforced concrete structure (SCCV) is developed for Japan Sodium-cooled Fast Reactor (JSFR). Although SC structure is generally in practical use, performance after exposing high temperature is not investigated. An experimental study including loading and/or heating tests has been carried out to investigate the fundamental structural features, which would be provided to develop methodology to evaluate the feasibility of SCCV under the severe conditions. In this paper, the design feature, the design and evaluation conditions for SCCV of JSFR as well as the construction method are summarized.
Negishi, Kazuo; Hosoya, Takusaburo; Sato, Kenichiro*; Somaki, Takahiro*; Matsuo, Ippei*; Shimizu, Katsusuke*
Proceedings of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09) (CD-ROM), p.9418_1 - 9418_7, 2009/05
An innovative containment vessel, namely Steel plate reinforced Concrete Containment Vessel (SCCV) is developed for Japan Sodium-Cooled Fast Reactor (JSFR). Reducing plant construction cost is one of the most important issues for commercialization of fast reactors. This study investigated construction issues including the building structure and the construction method as well as design issues in terms of the applicability of SCCV to fast reactors. An experimental study including loading and/or heating tests has been carried out to investigate the fundamental structural features, which would be provided to develop methodology to evaluate the feasibility of SCCV under the severe conditions. In this paper, the test plan is described as well as the first test results.
Kato, Atsushi; Negishi, Kazuo; Sato, Kenichiro*; Akiyama, Yo*; Hara, Hiroyuki*; Iwasaki, Mikinori*; Abe, Ganji*; Tokiyoshi, Takumi*; Okafuji, Takashi*; Umeki, Katsuhiko*; et al.
no journal, ,
Report research and development activities related to steel plate reinforced concrete containment vessel for the JSFR conducted as a part of METI commissioned research.
Eto, Masao*; Kamishima, Yoshio*; Okamura, Shigeki*; Negishi, Kazuo*; Sakamoto, Yoshihiko; Kawasaki, Nobuchika
no journal, ,
A concept of a compact reactor system for Japan Sodium-cooled Fast Reactor (JSFR) is being studied with aims including streamlining its facilities. A candidate of innovative technology for this purpose is a fuel exchange system which consists of an upper internal structure (UIS) with a radial slit and a single rotating plug, and another candidate is a "ot vessel" concept. The applicability of this structural concept has been studied by considering flow optimization, seismic resistance, thermal evaluation, etc. This paper reports the result of the applicability study.
Hara, Hiroyuki*; Negishi, Kazuo*; Kato, Atsushi; Akiyama, Yo*; Iwasaki, Mikinori*
no journal, ,
A containment vessel made of steel-plate-reinforced concrete (SCCV) is planned to be adopted to Japan Sodium-cooled Fast Reactor (JSFR), whose conceptual design is conducted in the Fast Reactor Cycle Technology Development (FaCT) project. The SCCV is a candidate of innovative technology aimed at improving quality and shortening construction period. Toward its commercialization, the project is developing methods to evaluate the structural integrity of the SCCV under elevated temperature and is also studying construction methods. Based on the research outcome, this paper reports the result of applicability study of the innovative technology.
Okamura, Shigeki*; Kamishima, Yoshio*; Negishi, Kazuo*; Kitamura, Seiji
no journal, ,
A horizontal seismic isolation system is planned to be adopted to Japan Sodium-cooled Fast Reactor (JSFR) as a candidate of innovative technology that suits conditions of fast reactors and reduces the load in the event of an earthquake. The aim of this system and its enhancing effect on seismic resistance in the periodic band specific to reactor structure have been examined. This paper reports the result of applicability study of the innovative technology.
Kato, Atsushi; Negishi, Kazuo; Akiyama, Yo*; Iwasaki, Mikinori*; Okafuji, Takashi*; Abe, Ganji*; Somaki, Takahiro*; Umeki, Katsuhiko*; Fukushima, Yasuaki*; Sawamoto, Yoshikazu*
no journal, ,
Steel plate reinforced concrete structure are adopted as the JSFR containment vessel to shorten a construction period. This reports project summary of SCCV Research and Development.
Kato, Atsushi; Negishi, Kazuo; Iwasaki, Mikinori*; Akiyama, Yo*; Furue, Mamoru*; Okayasu, Takafumi*
no journal, ,
Steel plate reinforced concrete structure are adopted as the JSFR containment vessel to shorten a construction period. This reports experimental investigation of SCCV basic structural property.
Kato, Atsushi; Negishi, Kazuo; Akiyama, Yo*; Iwasaki, Mikinori*; Abe, Ganji*; Okafuji, Takashi*
no journal, ,
Steel plate reinforced concrete structure are adopted as the JSFR containment vessel to shorten a construction period. This reports analysis method of SCCV barrier function.
Kato, Atsushi; Negishi, Kazuo; Akiyama, Yo*; Iwasaki, Mikinori*; Takami, Shinji*; Umeki, Katsuhiko*
no journal, ,
Steel plate reinforced concrete structure are adopted as the JSFR containment vessel to shorten a construction period. This reports experimental investigation of pull out strength of connecting stud.
Kato, Atsushi; Negishi, Kazuo; Akiyama, Yo*; Iwasaki, Mikinori*; Miyamoto, Keiichi*; Jodai, Akira*
no journal, ,
Steel plate reinforced concrete structure are adopted as the JSFR containment vessel to shorten a construction period. This reports experimental investigation of shear strength of connecting stud.
Negishi, Kazuo; Kawasaki, Nobuchika; Sakamoto, Yoshihiko; Kotake, Shoji; Okamura, Shigeki*; Kamishima, Yoshio*
no journal, ,
no abstracts in English
Yamamoto, Tomohiko; Negishi, Kazuo*; Hara, Hiroyuki*
no journal, ,
The JSFR adopts SCCV for the improvement of quality and economic efficiency. For commercialization of JSFR, we have carried out the research and development of not only the study on SCCV structure and construction term at the site but also the material strength test and analysis. These series presentation show the results. In this presentation, the results of study on construction methods are shown.