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Journal Articles

Development of high temperature isolation valve for the HTTR hydrogen production system

Nishihara, Tetsuo; Sakaki, Akihiro*; Inagaki, Yoshiyuki; Takami, Kazuo*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(4), p.381 - 387, 2004/12

JAERI has been carried out research and development on the HTTR hydrogen production system. One of the key components in this system is a high temperature isolation valve (HTIV) installed on the hot helium gas piping penetrating the reactor containment vessel. Angle valve with inner thermal insulator was selected for HTIV and conceptual design was performed. The structural integrity of HTIV was clarified by the stress analyses. Allowable helium leak rate of HTIV was discussed. Helium leak tests using small-scaled valve seat models were performed to decide the seat surface shape and valve closing force. The test results show that the leak rate of wedge shape seat increased in proportion to the number of simulated temperature and stress cycles loaded on the seat models before helium leak test, however that of flat seat did not depend on the number of cycles. So flat seat is adopted for HTIV. It was found that the seat closing force of 30 MPa is reasonable to meet the allowable helium leak rate.

JAEA Reports

Conceptual designs of near surface disposal facility for radioactive waste arising from the facilities using radioisotopes and research facilities for nuclear energy development and utilization

Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Yamamoto, Tadatoshi; Abe, Masayoshi

JAERI-Tech 2001-018, 88 Pages, 2001/03

JAERI-Tech-2001-018.pdf:5.66MB

no abstracts in English

JAEA Reports

Feasibility study on floating nuclear power plant, 1; Conceptual design study of FNPP (Contract research)

Yabuuchi, Noriaki; Takahashi, Masao*; Nakazawa, Toshio; Sato, Kazuo*; Shimazaki, Junya; Ochiai, Masaaki

JAERI-Research 2000-063, 69 Pages, 2001/02

JAERI-Research-2000-063.pdf:4.41MB

no abstracts in English

Journal Articles

Design study of a district-heating reactor installed in the basement of building

Kusunoki, Tsuyoshi; Odano, Naoteru; Nakajima, Nobuya; Fukuhara, Yoshifumi*; Ochiai, Masaaki

Nihon Genshiryoku Gakkai-Shi, 42(11), p.1195 - 1203, 2000/11

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Studies on sodium cooled fast breeder reactor

Nibe, Nobuaki; Shimakawa, Yoshio; ; Hayafune, Hiroki; ; ;

JNC TN9400 2000-074, 388 Pages, 2000/06

JNC-TN9400-2000-074.pdf:13.32MB

Large sized sodium-cooled fast breeder reactors of large-size are being studied and have been operated in Japan and many countries. ln this feasibility study, evaluation was made on technical feasibinty for design concepts or 1 loop type and 3 pool types, specially from the viewpoint of improvement of economical competence. The design concepts include the ideas of cost reduction measures such as large-scaled components, reduction of loop number and integration of components on the basic of utilization of sodium characteristics. From the results of the evaluation, it may be possible for all the concepts to attain the economical target of 200 thousands yen per kilowatt, though further confirmation should be made for technical feasibility of those concepts. ln addition, the following items were listed up as further cost-reduction measures. (1)Higher temperature cooling system and steam cycle efficiency (2)Shortening of construction term (3)Reduction of safety systems by using measuring instruments with high performmce (4)Adoption of SG-ACS

JAEA Reports

Report on neutronic design calculational methods

; *; *; *

JNC TN8410 2000-011, 185 Pages, 2000/05

JNC-TN8410-2000-011.pdf:4.67MB

This report describes the neutronic design calculational methods used in Fuel Design and Evaluation Group in order to inform other related sections of FBR core analysis technology and hand down the technology. Especially we show the neutronics calculation procedures used for the conceptual design study of the advanced core with 127 pin bundle for MONJU that has been carried out in our group. The topics include effective cross section preparation calculations, two-dimensional depletion calculations, three-dimensional diffusion calculations, reactivity coefficient calculations, and control rod worth calculations. The calculational methods shown in this report are the standard neutronics calculation methods employed in our group at the moment. However, the improvement of calculation codes, the reduction of correction factors and uncertainties for design using the nuclear data obtained in the start-up test for MONJU and so on, and the update of nuclear data file will be planned in order to improve evaluation accuracies. Those may change the neutronic design calculational methods, but we decided to describe the present standard calculational methods in our group from the viewpoint of sharing information in JNC.

JAEA Reports

System concept for FBR cycle data base

Kofuji, Hirohide; ; *; *;

JNC TN9400 2000-055, 49 Pages, 2000/03

JNC-TN9400-2000-055.pdf:2.07MB

Accompanying with the progress of the "Feasibility study on FBR cycle system; FS" , various kinds of technical information, facility design parameters, and related data will be obtained and they should be stored in data bases and be used as fundamental data for the FS. So the several data bases are going to be set up at each section and controlled by the management system through a local area network. Among above data bases, a prototype of FBR cycle data base that will record data for FBR scenario study and synthetic assessment is to be completed in. Phase l by fiscal year 2000, so the data base system concept has been examined in the current fiscal year, 1999. As the results of the system concept examination, two types of prototypes have been selected, one is to be set up as the data table containing digital data that are extracted from technical papers, another is as image data of papers with index information. Referring to examples of data bases in other companies, it was kept in mind to use a package software for general purpose and to utilize data existing now.

JAEA Reports

None

*; *

JNC TJ8420 2000-010, 171 Pages, 2000/03

JNC-TJ8420-2000-010.pdf:5.34MB

no abstracts in English

JAEA Reports

None

Shinohara, Yoshinori*; Tsujimoto, Keiichi*

JNC TJ1400 2000-002, 280 Pages, 2000/02

JNC-TJ1400-2000-002.pdf:9.57MB

no abstracts in English

JAEA Reports

None

Shinohara, Yoshinori*; Tsujimoto, Keiichi*

JNC TJ1400 2000-001, 137 Pages, 2000/02

JNC-TJ1400-2000-001.pdf:4.19MB

no abstracts in English

JAEA Reports

Operation system concept for high-level radioactive wastes disposal facility

*; *; Tanai, Kenji

JNC TN8400 99-050, 94 Pages, 1999/11

JNC-TN8400-99-050.pdf:3.86MB

This paper reports on the evaluations of operational activities for a High Level Radioactive Wastes Disposal Facility, from initial acceptance of vitrified waste at a surface facility to emplacement engineered barriers in underground facilities. The purpose of this analysis is to confirm the technical feasibility of geological disposal. First, the basic design and repository system requirements are identified. Second, operational activities in surface facilities, access facilities and underground facilities are described. The required procedures and equipment, suitable for specific emplacement concepts and configurations for engineered barrier systems are discussed for specific examples. Countermeasures for potential adverse events or conditions are based on extensive civil engineering and mining experiences in Japan and abroad. The time schedule is also evaluated on the basis of these concepts. In addition, the concept of stationary and mobile radiation control areas is studied based on experiences and practice in current nuclear facilities. Finally future research and development items are summarized.

JAEA Reports

None

Shinohara, Yoshinori*; *

JNC TJ1400 99-044, 349 Pages, 1999/06

JNC-TJ1400-99-044.pdf:13.24MB

no abstracts in English

JAEA Reports

None

Shinohara, Yoshinori*; *

JNC TJ1400 99-043, 101 Pages, 1999/06

JNC-TJ1400-99-043.pdf:3.56MB

no abstracts in English

JAEA Reports

Development of dynamic simulation code for fuel cycle of fusion reactor

Aoki, Isao; Seki, Yasushi; *; *; Kim, Y.*

JAERI-Data/Code 99-004, 136 Pages, 1999/02

JAERI-Data-Code-99-004.pdf:5.82MB

no abstracts in English

Journal Articles

Conceptual designing of water-cooled reactors with increased or reduced moderation

Okubo, Tsutomu; Kugo, Teruhiko; *; Shimada, Shoichiro*; Ochiai, Masaaki

Proc. of Workshop on Advanced Reactors with Innovative Fuels, p.127 - 137, 1998/10

no abstracts in English

JAEA Reports

A Conceptual design study of superconducting proton linac for neutron science project, 1

Honda, Yoichiro*; Hasegawa, Kazuo; Ouchi, Nobuo; Kusano, Joichi; *; Mizumoto, Motoharu

JAERI-Tech 98-040, 77 Pages, 1998/09

JAERI-Tech-98-040.pdf:3.27MB

no abstracts in English

JAEA Reports

None

*; *; *; *

PNC TJ1277 98-002, 74 Pages, 1998/02

PNC-TJ1277-98-002.pdf:3.05MB

None

JAEA Reports

None

PNC TJ1211 98-005, 62 Pages, 1998/02

PNC-TJ1211-98-005.pdf:2.65MB

None

JAEA Reports

None

*; *; *; *

PNC TJ1211 98-004, 138 Pages, 1998/02

PNC-TJ1211-98-004.pdf:4.95MB

None

55 (Records 1-20 displayed on this page)