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Saito, Shigeru; Meigo, Shinichiro; Makimura, Shunsuke*; Hirano, Yukinori*; Tsutsumi, Kazuyoshi*; Maekawa, Fujio
JAEA-Technology 2023-025, 48 Pages, 2024/03
JAEA-Technology-2023-025.pdf:3.11MB
JAEA has been developing Accelerator-Driven Systems (ADS) for research and development of nuclear transmutation using accelerators in order to reduce the volume and hazardousness of high-level radioactive waste generated by nuclear power plants. In order to prepare the material irradiation database necessary for the design of ADS and to study the irradiation effects in Lead-Bismuth Eutectic (LBE) alloys, a proton irradiation facility is under consideration at J-PARC. In this proton irradiation facility, 250 kW proton beams will be injected into the LBE spallation target, and irradiation tests under LBE flow will be performed for candidate structural materials for ADS. Furthermore, semiconductor soft-error tests, medical RI production, and proton beam applications will be performed. Among these, Post Irradiation Examination (PIE) of irradiated samples and RI separation and purification will be carried out in the PIE facility to be constructed near the proton irradiation facility. In this PIE facility, PIE of the equipment and samples irradiated in other facilities in J-PARC will also be performed. This report describes the conceptual study of the PIE facility, including the items to be tested, the test flow, the facilities, the test equipment, etc., and the proposed layout of the facility.
Saito, Shigeru; Wan, T.*; Okubo, Nariaki; Obayashi, Hironari; Watanabe, Nao; Ohdaira, Naoya*; Kinoshita, Hidetaka; Yamaki, Kenichi*; Kita, Satoshi*; Yoshimoto, Hidemitsu*; et al.
JPS Conference Proceedings (Internet), 33, p.011041_1 - 011041_6, 2021/03
An Accelerator Driven System (ADS) for waste transmutation investigated in JAEA employs lead-bismuth eutectic (LBE) as a neutron production target material and coolant. The neutrons are to be produced via the spallation with 1.5 GeV proton beam injection. As materials irradiation data are important for ADS development, JAEA plans to construct an irradiation facility with LBE neutron production target in J-PARC. There are many technical issues on LBE for practical use. In JAEA, various R&Ds are being carried out. Concerning corrosion study, conditioning operation and functional tests of OLLOCHI started. Oxygen concentration control technology has also developing. In the large scale LBE loop experiment, the operation for steady state and transient experiments was performed by using IMMORTAL. In the area of instrument, development of ultrasonic flow meter and freeze seal valve are progressing as a key technology for the LBE loop system. Investigation of behavior of impurities in LBE, which is important for design of the irradiation facility, started. In this paper, the status of the LBE studies and experimental plan will be presented.
Tamada, Masao
Genshiryoku Nenkan 2016, p.148 - 152, 2015/10
Takasaki Advanced Radiation Research Institute (TARRI) was established in April 1963. There are irradiation facilities of quantum beam such as ion, electron, Co-60 
-rays. TARRI has researched as complementary utilization together with other quantum beams such as neutron, synchrotron radiation, etc. as a part of the quantum beam platform. Recent technology transfer are outcomes of mutation-breeding sake yeast for quality sake brewed from the finest rice and cesium removal adsorbent for cartridge-type filters. Radiation-induced crosslinked resin was commercialized recently as a school teaching material. Dissemination of radiation technology has been continued through outreach activities.
Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Hirakawa, Yasushi; Furukawa, Tomohiro; Hoashi, Eiji*; Fukada, Satoshi*; Suzuki, Akihiro*; Yagi, Juro*; Tsuji, Yoshiyuki*; et al.
Proceedings of Plasma Conference 2014 (PLASMA 2014) (CD-ROM), 2 Pages, 2014/11
In the IFMIF/EVEDA (International Fusion Materials Irradiation Facility/ Engineering Validation and Engineering Design Activity), the validation tests of the EVEDA lithium test loop with the world's highest flow rate of 3000 L/min was succeeded in generating a 100 mm-wide and 25 mm-thick free-surface lithium flow steadily under the IFMIF operation condition of a high-speed of 15 m/s at 250
C in a vacuum of 10 
Pa. Some excellent results of the recent engineering validations including lithium purification, lithium safety, and remote handling technique were obtained, and the engineering design of lithium facility was also evaluated. These results will advance greatly the development of an accelerator-based neutron source to simulate the fusion reactor materials irradiation environment as an important key technology for the development of fusion reactor materials.
Okumura, Yoshikazu
Proceedings of 11th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.194 - 198, 2014/10
International Fusion Materials Irradiation Facility (IFMIF) is one of the major facilities in fusion program to irradiate and characterize the fusion materials under intense neutron field. Under the framework of Broader Approach (BA) agreement between Japan and Euratom, Engineering Validation and Engineering Design Activities (EVEDA) launched in 2007 in Japan to validate the key technologies to realize IFMIF. The most critical technology to realize IFMIF is two set of linear accelerators each producing 125mA/CW deuterium ion beams up to 40MeV. The prototype accelerator being developed in EVEDA consists of an injector, a RFQ accelerator, and a superconducting linac, whose target is to produce 125mA/CW deuterium ion beams up to 9MeV. The injector has been delivered to International Fusion Energy Research Center (IFERC) in Rokkasho, Japan, where all the accelerator components will be assembled and operated to validate the accelerator technologies required for IFMIF.
Kanazawa, Takao
Kigyo Sapoto Gumma, 10 Pages, 2004/05
no abstracts in English
raysHaruyama, Yasuyuki
Kigyo Sapoto Gumma, P. 13, 2004/04
Outline of cobalt-60 -ray facilities for radiation processing is described. It consists of characteristics of cobalt-60 source, components of the facility, and radiation safety systems. Typical products in -ray processing are also shown.
Sudo, Yukio
Hoshasen To Sangyo, (100), p.10 - 11, 2003/12
no abstracts in English
Kume, Tamikazu
Radioisotopes, 51(11), p.522 - 532, 2002/11
no abstracts in English
Yutani, Toshiaki*; Nakamura, Hiroo; Sugimoto, Masayoshi; Takeuchi, Hiroshi
Fusion Science and Technology, 41(3), p.850 - 853, 2002/05
no abstracts in English
Takeuchi, Hiroshi; Sugimoto, Masayoshi; Nakamura, Hiroo; Yutani, Toshiaki*; Ida, Mizuho*; Jitsukawa, Shiro; Kondo, Tatsuo; Matsuda, Shinzaburo; Matsui, Hideki*; Shannon, T. E.*; et al.
Fusion Energy 2000 (CD-ROM), 5 Pages, 2001/00
no abstracts in English
Kinsho, Michikazu; Sugimoto, Masayoshi; Seki, Masakazu; Oguri, Hidetomo; Okumura, Yoshikazu
Review of Scientific Instruments, 71(2), p.963 - 965, 2000/02
Times Cited Count：1 Percentile：20.02(Instruments & Instrumentation)no abstracts in English
JAERI-Review 99-014, p.104 - 0, 1999/04
no abstracts in English
Yoshii, Fumio
Hoshasen Kagaku, (65), p.47 - 49, 1998/00
no abstracts in English
Konishi, Satoshi; Yamaki, Daiju; Katsuta, Hiroji; M
slang, A.*; R.Jameson*; Martone, M.*; Shannon, T. E.*
JAERI-Tech 97-056, 9 Pages, 1997/11
no abstracts in English
*; Nakamura, Hideo; *; ; Maekawa, Hiroshi
Eighth Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), 3, p.1276 - 1283, 1997/00
no abstracts in English
Tanaka, Ryuichi; Yotsumoto, Keiichi; Watanabe, Hiromasa
Radioisotopes, 45(3), p.213 - 220, 1996/03
no abstracts in English
Sunaga, Hiromi; *
Hoshasen To Sangyo, 0(65), p.22 - 29, 1995/00
no abstracts in English
Sugimoto, Masayoshi; Noda, Kenji
Proc. of the 1994 Int. Linac Conf., 2, p.842 - 844, 1995/00
no abstracts in English
