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Journal Articles

Investigation of the ground-state spin inversion in the neutron-rich $$^{47,49}$$Cl isotopes

Linh, B. D.*; Corsi, A.*; Gillibert, A.*; Obertelli, A.*; Doornenbal, P.*; Barbieri, C.*; Chen, S.*; Chung, L. X.*; Duguet, T.*; G$'o$mez-Ramos, M.*; et al.

Physical Review C, 104(4), p.044331_1 - 044331_16, 2021/10

no abstracts in English

Journal Articles

Temperature stability of PIN-PMN-PT ternary ceramics during pyroelectric power generation

Moro, Takuya*; Kim, J.*; Yamanaka, Satoru*; Murayama, Ichiro*; Kato, Takanori*; Nakayama, Tadachika*; Takeda, Masatoshi*; Yamada, Noboru*; Nishihata, Yasuo; Fukuda, Tatsuo; et al.

Journal of Alloys and Compounds, 768, p.22 - 27, 2018/11

 Times Cited Count:10 Percentile:66.99(Chemistry, Physical)

JAEA Reports

Study on Advanced Structural Design for Commercialized Fast Breeder Reactors

Morishita, Masaki; Kitamura, Seiji; Takahashi, Kenji; Inoue, Kazuhiko; Kida, Masanori; Moro, Satoshi*; Kato, Asao*; Fushimi, Minoru*

JNC TY9400 2004-028, 921 Pages, 2004/11

Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Power Company (JAPC) launched joint research programs on structural design and three-dimensional seismic isolation technologies, as part of the supporting R&D activities for the feasibility studies on commercialized fast breeder reactor cycle systems. A research project by JAPC under the auspices of the Ministry of Economy, Trade, and Industry (METI) with technical support by JNC is included in this joint study. This report contains the results of the research on the structural design technology. The research scope was identified as (1) Study on Developing Program, (2) Study on 3-dimentional Entire Building Base Isolation System, and (3) Study on Vertical Isolation System for Main Equipment, and the results of this year's studies are summarized as follows. (1) Study on Developing Program -Performance Requirements for 3-dimensional Isolation Devices "The behavior of a three-dimensional isolated reactor building" and "amenity under the strong wind load" were studied in order to set up performance requirements for the three-dimensional isolation system. Consequently, it was proved for the former subject that the structure of horizontal base-dimensional isolated building was applicable to 3-D isolated building and for the latter that amenity of the operator in the 3-D isolated reactor building is not affected under the strong wind. -Development Targets and Schedules for Three-dimensional Isolation Deviece In order to select the development candidate of the three dimensional isolation devices, "evaluation items and criteria" and "technical guideline on seismic three-dimensional isolation system" were studied. For the former subject, detailed requirements to the component in the reactor building were studied based on the 2002 fiscal year result and embodied.(2) Study on 3-dimentional Entire Building Base Isolation System -The 3 system concepts nominated on 2001, "Hydraulic system", "Fiber reinforced air sp

Journal Articles

Study on vertical component seismic isolation system with coned disk spring

Kitamura, Seiji; Ito, Kei; Moro, Satoshi

ASME PVP 2004, 486(2), p.61 - 67, 2004/07

The outline of the vertical seismic isolation system for component and a series of model tests with full scale coned disk spring and damper are shown in this paper.

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

Study on Advanced Structural Design for Commercialized Fast Breeder Reactors

Morishita, Masaki; Kitamura, Seiji; Inoue, Kazuhiko; Kida, Masanori; Moro, Satoshi; Kato, Asao; Fushimi, Minoru*

JNC TY9400 2003-009, 682 Pages, 2003/05

JNC-TY9400-2003-009.pdf:35.1MB

Japan Nuclear Cycle Development Institute(JNC) and Japan Atomic Power Company (JAPC) launched joint research programs on structural design and three-dimensional seismic isolation technologies,as part of the supporting R&D activities for the feasibility studies on commercialized fast breeder reactor cycle systems. A research project by JAPC under the auspices of the Ministry of Economy,Trade,and Industry (METI) with technical support by JNC is included in this joint study. This report contains the results of the research on the structural design technology. The research scope was identified as (1) Study on Developing Program,(2) Study on 3-dimentional Entire Building Base Isolation System,and (3) Study on Vertical Isolation System for Main Equipment, and the results of this year's studies are summarized as follows.

Journal Articles

A Development Program of Three-dimensional Seismic Isolation for Advanced Reactor Systems in Japan

Moro, Satoshi; Ito, Kei; Midorikawa, Saburo*

Transactions of 17th International Conference on Structural Mechanics in Reactor Technology (SMiRT-17), CD-R, K09-1 Pages, 2003/01

None

Journal Articles

Development of 3D Seismic Isolation Techology for Advanced Nuclear Power Plant Application

Moro, Satoshi; Ito, Kei; Kitamura, Seiji

Proceedings of International Conference on Advanced Nuclear Power (GENES4/ANP2003) (CD-ROM), P. 1110, 2003/00

None

Journal Articles

Design study an advanced nuclear fuel recycling system; Conceptual design of recycling system using dry reprocessing technology

; ; Moro, Satoshi; Yonezawa, Shigeaki; ; Tozawa, Katsuhiro

Proceedings of International Conference on Future Nuclear Systems (GLOBAL'99), 0 Pages, 1999/00

None

Journal Articles

None

; ; Moro, Satoshi; ; ;

Saikuru Kiko Giho, (1), p.31 - 40, 1998/12

None

JAEA Reports

Designstudy on advanced nuclear fuel recycle system; Conceptual design study of recycle system using molten salt

; ; Moro, Satoshi; ; ; ;

JNC TN9400 98-003, 422 Pages, 1998/10

JNC-TN9400-98-003.pdf:21.36MB

Advanced recycle system engineering group of OEC has being carried out a design study of the advanced nuclear fuel recycle system using molten salt (electro-metallurgical process). This system is aiming for improvements of fuel cycle economy and reduction of environmental burden (MA recycles, Mimmum of radioactive waste disposal), and also improvement of safety and nuclear non-proliferation. This report describes results of the design study that has been continued since December 1996. (1)A design concept of the advanced nuclear fuel recycle system, that is a module type recycle system of pyrochemical reprocessing and fuel re-fabrication was studied. The module system has advantage in balance of Pu recycle where modules are constructed in coincidence with the construction plan of nuclear power plants, and also has flexibility for technology progress. A demonstration system, minimum size of the above module, was studied. This system has capacity of 10 tHM/y and is able to demonstrate recycle technology of MOX fuel, metal fuel and nitride fuel. (2)Each process of the system, which are pyrochemical electrorefining system, cathode processor, de-cladding system, waste disposal system, etc., were studied. In this study, capacity of an electrorefiner was discussed, and vitrification experiment of molten salt using lead-boric acid glass was conducted. (3)A hot cell system and material handling system of the demonstration system was studied. A robot driven by linear motor was studied for the handling system, and an arrangement plan of the cell system was made. Criticality analysis in the cell system and investigation of material accountancy system of the recycle plant were also made. This design study will be continued in coincidence with design study of reactor and fuel, aiming to establish the concept of FBR recycle system.

JAEA Reports

Report of researchers' meeting on advanced nuclear fuel recycle system; Nuclear fuel recycle system and technology to be aimed and its research & development

; Moro, Satoshi; ; ; ;

PNC TN9410 98-033, 284 Pages, 1998/03

PNC-TN9410-98-033.pdf:9.34MB

System engineering division of OEC has being carried out a design study of the advanced nuclear fuel recycle system using electro-metallurgical process, aiming for improvements in safety, reliability, economy and a1so in environmental burden and nuclear non-proliferation. But the public criticism against nuclear power is more severe recently, and the situation is changing as seeing in the conclusion of the round-table conference on FBR. The researcher's meetings, in which researchers in PNC and from other organizations attended, were held during December, 1997 and March, 1998 in order to discuss on the advanced nuclear fuel recycle system and technology for FBR to be aimed in the future, and how to execute its research & development, etc. The conclusions of this meeting are as follows: (1)The future advanced FBR fuel cycle system shall be the system which has high potential for maximum utilization of uranium resources, and also for revolutionary improvements of economy, safety, environmental burden, etc. so as to be accepted in the society. (2)Regarding to the process of the future fuel eycle system, electro-metallurgical process that is able to apply for reprocessing of different types of fuel (oxide, metal and nitride) and is flexible for technical progress is recommended. Research & development of this system and technology shall be carried out. (3)The mission of PNC (new organization) is to select the most appropriate advanced FBR fuel cycle system from the viewpoint of the long-term FBR age in the future, and to conduct development of its system. It is expected for the new organization to execute its research and development steadily in cooperation with other research institutes, etc. under the nation-wide assessment and agreement. According to the above conclusions, the system engineering division will enhance the design study of the advanced FBR fuel cycle system and establish the definite concept of the system in cooperation with concerned in and ...

Journal Articles

None

; *; Moro, Satoshi; *

Nihon Genshiryoku Gakkai-Shi, 29(1), p.48 - 57, 1987/01

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

13 (Records 1-13 displayed on this page)
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