Analysis of sequential charged particle reaction experiments for fusion reactors

Yamauchi, Michinori*; Hori, Junichi*; Ochiai, Kentaro; Sato, Satoshi; Nishitani, Takeo; Kawasaki, Hiromitsu*

Fusion Engineering and Design, 81(8-14), p.1577 - 1582, 2006/02

https://doi.org/10.1016/j.fusengdes.2005.09.066

no abstracts in English

Microstructural development and radiation hardening of neutron irradiated Mo-Re alloys

Nemoto, Yoshiyuki; Hasegawa, Akira*; Sato, Manabu*; Abe, Katsunori*; Hiraoka, Yutaka*

Journal of Nuclear Materials, 324(1), p.62 - 70, 2004/01

https://doi.org/10.1016/j.jnucmat.2003.09.007

In this study, stress-relieved specimens and recrystallized specimens of pure Mo and Mo-Re alloys (Re content=2,4,5,10,13 and 41wt%) were neutron irradiated up to 20dpa at various temperatures (681-1072K). On microstructure observation, sigma phase and chi phase precipitates were observed in all irradiated Mo-Re alloys. Voids were observed in all irradiated specimen, and dislocation loops and dislocations were observed in the specimens that were irradiated at lower temperatures. On Vickers hardness testing, all of the irradiated specimens showed hardening. Especially Mo-41Re were drastically embrittled after irradiation at 874K or less. From these results, authors discuss about relation between microstructure development and radiation hardening, embrittlement, and propose the most efficient Re content and thermal treatment for Mo-Re alloys to be used under irradiation condition.

Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H

Jitsukawa, Shiro; Tamura, Manabu*; Van der Schaaf, B.*; Klueh, R. L.*; Alamo, A.*; Petersen, C.*; Schirra, M.*; Spaetig, P.*; Odette, G. R.*; Tavassoli, A. A.*; et al.

Journal of Nuclear Materials, 307-311(Part1), p.179 - 186, 2002/12

https://doi.org/10.1016/S0022-3115(02)01075-9

Reduced activation ferritic/martensitic steel is the primary candidate structural material for ITER Test Blanket Modules and DEMOnstration fusion reactor because of its excellent dimensional stability under irradiation and lower residual activity as compared with the Ni bearing steels such as the austenitic stainless steels. In this paper, microstructural features, tensile, fracture toughness, creep and fatigue properties of a reduced activation martensitic steel F82H (8Cr-2W-0.04Ta-0.1C) are reported before and after irradiation, in addition to the design concept used for development of this alloy. A large number of collaborative test results including those generated under the IEA working group implementing agreements are collected and are used to evaluate the feasibility of use of F82H steel as one of the reference alloys. The effect of metallurgical variables on the irradiation hardening is reviewed and compared with the results obtained from irradiation experiments.

Report of Joint Research Committee for Fusion Reactor and Materials; July 16, 2001, Tokyo, Japan

Research Committee for Fusion Reactor; Research Committee for Fusion Materials

JAERI-Review 2002-008, 79 Pages, 2002/03

JAERI-Review-2002-008.pdf:9.92MB

Joint research committee for fusion reactor and materials was held in Tokyo on July 16, 2001. In the committee, a review of the development programs and the present status on the blanket technology, materials and IFMIF(International Fusion Materials Irradiation Facility) in JAERI and Japanese Universities was reported, and the direction of these R&D was discussed. Moreover, the progress of the collaboration between JAERI and Japanese Universities was discussed. This report consists of the summaries of the presentations and the viewgraphs which were used at the committee.

Thermal stress analyses in first wall subjected to high heat flux from fusion plasma

Kurihara, Ryoichi; Nishio, Satoshi; Konishi, Satoshi

Thermal Stresses 2001, p.81 - 84, 2001/00

no abstracts in English

Proceedings of the Symposium on the Joint Research Project between JAERI and Universities; Status and Perspective of the Advanced Radiation Technology Project, January 27, 1999, National Education Center, Tokyo, Japan

Committee for the Joint Research Project on the Advanced Radiation Technology; Committee for the Collaborative Research on the Advanced Radiation Technology

JAERI-Conf 2000-008, 113 Pages, 2000/06

JAERI-Conf-2000-008.pdf:11.5MB

no abstracts in English

Effect of activation cross section change on the shallow land burial fraction of low activation materials for fusion reactors

Seki, Yasushi; Aoki, Isao; Ueda, Shuzo; Nishio, Satoshi; Kurihara, Ryoichi; Tabara, Takashi*

Fusion Technology, 34(3), p.353 - 357, 1998/11

no abstracts in English

Social acceptability and scientific prospect of fusion energy, 7; Safety

Seki, Yasushi

Purazuma, Kaku Yugo Gakkai-Shi, 74(8), p.795 - 801, 1998/08

https://ci.nii.ac.jp/naid/110003827461

no abstracts in English

Joint report of JAERI/USDOE collaborative program on fusion neutronics; Induced radioactivity measurements in fusion neutron environment

Ikeda, Yujiro; A.Kumar*; Konno, Chikara; Kosako, Kazuaki*; Oyama, Yukio; ; Maekawa, Hiroshi; M.Z.Youssef*; M.A.Abdou*

JAERI-M 93-018, 164 Pages, 1993/02

JAERI-M-93-018.pdf:4.96MB

no abstracts in English

Concept study of the Steady State Tokamak Reactor(SSTR)

JAERI-M 91-081, 607 Pages, 1991/06

JAERI-M-91-081.pdf:15.66MB

no abstracts in English