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Journal Articles

A Plan of materials irradiation facility at J-PARC for development of ADS and high-power accelerator facilities

Maekawa, Fujio

JPS Conference Proceedings (Internet), 33, p.011042_1 - 011042_6, 2021/03

Development of beam window (BW) materials is one of crucial issues in development of accelerator driven nuclear transmutation systems (ADS). The BW is exposed to high energy protons and spallation neutrons, and also to corrosive lead-bismuth eutectic (LBE) alloy at high temperature of about 500$$^{circ}$$C. Recently, not only high-power accelerators but also high-power targets are the rate-limiting factor for increasing the power of accelerator facilities in terms of radiation damage and heat removal. To study radiation damage on BW and target materials for high-power accelerator facilities including ADS, we are planning a materials irradiation facility by utilizing the proton beam of 400 MeV and 250 kW provided by the J-PARC's Linac. The target is flowing LBE alloy which is a candidate target and coolant material of ADS. When a steel sample is irradiated in the target for one year, the sample receives radiation damage of about 10 dpa at maximum which is equivalent to the yearly radiation damage of ADS's BW. In the current facility concept, the facility is equipped with a hot-laboratory for efficient post-irradiation examination. The facility will be outlined in this presentation.

Journal Articles

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

 Times Cited Count:35 Percentile:89.49(Materials Science, Multidisciplinary)

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.

JAEA Reports

IFMIF-KEP; International Fusion Materials Irradiation Facility key element technology phase report

IFMIF International Team

JAERI-Tech 2003-005, 559 Pages, 2003/03

JAERI-Tech-2003-005.pdf:48.89MB

The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based D-Li neutron source designed to produce an intense neutron field that will simulate the neutron environment of a D-T fusion reactor. IFMIF will provide a neutron flux equivalent to 2 MW/m$$^{2}$$, 20 dpa/y in Fe, in a volume of 500 cm$$^{3}$$ and will be used in the development and qualification of materials for fusion systems. The design activities of IFMIF are performed under an IEA collaboration which began in 1995. In 2000, a three-year Key Element Technology Phase (KEP) of IFMIF was undertaken to reduce the key technology risk factors. This KEP report describes the results of the three-year KEP activities in the major project areas of accelerator, target, test facilities and design integration.

JAEA Reports

Data on post irradiation experiments of heat resistant ceramic composite materials; PIE for 97M-13A

Baba, Shinichi; Ishihara, Masahiro; Sozawa, Shizuo; Sekino, Hajime

JAERI-Data/Code 2003-003, 394 Pages, 2003/03

JAERI-Data-Code-2003-003.pdf:13.63MB

The research on the radiation damage mechanism of heat resistant ceramic composite materials is one of the research subjects of the innovative basic research in the field of high temperature engineering, using the High Temperature engineering Test Reactor (HTTR). Three series of irradiation tests on the heat resistant ceramic composite materials, first to third irradiation test program, were carried out using the Japan Material Testing Reactor (JMTR). This is a summary report on the the first irradiation test program; irradiation induced dimensional change, thermal expansion coefficient, X-ray diffraction and $$gamma$$-ray spectrum are reported.

Journal Articles

New in-pile water loop facility for IASCC studies at JMTR

Tsukada, Takashi; Komori, Yoshihiro; Tsuji, Hirokazu; Nakajima, Hajime; Ito, Haruhiko

Proceedings of International Conference on Water Chemistry in Nuclear Reactor Systems 2002 (CD-ROM), 5 Pages, 2002/00

Irradiation assisted stress corrosion cracking (IASCC) is caused by the synergistic effects of neutron and gamma radiation, residual and applied stresses and high temperature water environment on the structural materials of vessel internals. IASCC has been studied since the beginning of the 1980s and the phenomenological knowledge on IASCC is accrued extensively. However, mainly due to the experimental difficulties, data for the mechanistic understanding and prediction of failures of the specific in-vessel components are still insufficient and further well-controlled experiments are needed [1]. In recent years, efforts to perform the in-pile materials test for IASCC study have been made at some research reactors [2-4]. At JAERI, a high temperature water loop facility was designed to install at the Japan Materials Testing Reactor (JMTR) to carry out the in-core IASCC testing. This report describes an overview of design and specification of the loop facility.

JAEA Reports

Results and future plans for the innovative basic research on high temperature engineering

HTTR Utilization Research Committee

JAERI-Review 2001-016, 232 Pages, 2001/05

JAERI-Review-2001-016.pdf:12.01MB

no abstracts in English

JAEA Reports

Journal Articles

ITER materials R&D data bank

Tanaka, Shigeru; R.Matera*; G.Kalinin*; V.Barabash*; Mori, Kensuke*

Journal of Nuclear Materials, 271-272, p.478 - 485, 1999/00

 Times Cited Count:4 Percentile:35.45(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

JAEA Reports

Neutorn spectral tailoring calculation in the JMTR; Feasible study on irradiation test simulating the fusion reactor condition

Nagao, Yoshiharu; Shimakawa, Satoshi; ;

JAERI-Tech 95-006, 46 Pages, 1995/02

JAERI-Tech-95-006.pdf:1.45MB

no abstracts in English

Journal Articles

Development of neutron damage studies; US-Japan joint irradiation experiment on structural materials

Hishinuma, Akimichi

Purazuma, Kaku Yugo Gakkai-Shi, 70(7), p.719 - 725, 1994/07

no abstracts in English

Journal Articles

Dielectric and electrical design consideration of ceramics for fusion devices

Ono, Hideo

Journal of Nuclear Materials, 179-181, p.60 - 63, 1991/00

 Times Cited Count:5 Percentile:54.3(Materials Science, Multidisciplinary)

no abstracts in English

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