Materials and Life Science Experimental Facility (MLF) at the Japan Proton Accelerator Research Complex, 2; Neutron scattering instruments

Nakajima, Kenji; Kawakita, Yukinobu; Ito, Shinichi*; Abe, Jun*; Aizawa, Kazuya; Aoki, Hiroyuki; Endo, Hitoshi*; Fujita, Masaki*; Funakoshi, Kenichi*; Gong, W.*; et al.

Quantum Beam Science (Internet), 1(3), p.9_1 - 9_59, 2017/12

https://doi.org/10.3390/qubs1030009

The neutron instruments suite, installed at the spallation neutron source of the Materials and Life Science Experimental Facility (MLF) at the Japan Proton Accelerator Research Complex (J-PARC), is reviewed. MLF has 23 neutron beam ports and 21 instruments are in operation for user programs or are under commissioning. A unique and challenging instrumental suite in MLF has been realized via combination of a high-performance neutron source, optimized for neutron scattering, and unique instruments using cutting-edge technologies. All instruments are/will serve in world-leading investigations in a broad range of fields, from fundamental physics to industrial applications. In this review, overviews, characteristic features, and typical applications of the individual instruments are mentioned.

Sulfate complexation of element 104, Rf, in HSO/HNO mixed solution

Li, Z.*; Toyoshima, Atsushi; Asai, Masato; Tsukada, Kazuaki; Sato, Tetsuya; Sato, Nozomi; Kikuchi, Takahiro; Nagame, Yuichiro; Schdel, M.; Pershina, V.*; et al.

Radiochimica Acta, 100(3), p.157 - 164, 2012/03

https://doi.org/10.1524/ract.2012.1898

Microstructure formation and in situ phase identification from undercooled Co-61.8 at.% Si melts solidified on an electromagnetic levitator and an electrostatic levitator

Li, M.*; Nagashio, Kosuke*; Ishikawa, Takehiko*; Mizuno, Akitoshi*; Adachi, Masayoshi*; Watanabe, Masahito*; Yoda, Shinichi*; Kuribayashi, Kazuhiko*; Katayama, Yoshinori

Acta Materialia, 56(11), p.2514 - 2525, 2008/06

https://doi.org/10.1016/j.actamat.2008.01.041

Co-61.8 at.% Si (CoSe-CoSi) eutectic alloys were solidified on an electromagnetic levitator (EML) and an electrostatic levitator (ESL) at different undercooling levels. The results indicated that there is only a single recalescence event at low undercooling with the CoSi intermetallic compound as primary phase, which is independent of processing facilities, on either an EML or an ESL. The microstructure, however, is strongly dependent on the processing facility. On high undercooling, double recalescence takes place regardless of levitation condition. In situ X-ray diffraction of alloys solidified on the EML demonstrates that the CoSi compound becomes the primary phase upon the first recalescence, and the CoSi intermetallic phase crystallizes during the second recalescence. In addition to phase identification, real-time diffraction patterns can also provide additional evidence of the fragmentation of the primary phase.

Progress of R&D on geological disposal of high-level radioactive waste (HLW) in Japan

Ishikawa, Hirohisa; Igarashi, Hiroshi; Umeki, Hiroyuki; Shimizu, Kazuhiko; Miyahara, Kaname; Ishimaru, Tsuneari; Mitsui, Seiichiro

Proceedings of 6th Pacific Rim Conference on Ceramic and Glass Technology (PacRim6) (CD-ROM), 17 Pages, 2006/09

Final disposal of high-level radioactive waste is essential issue to utilize nuclear energy. JNC has promoted the research and development on disposal technology to contribute to the implementation and safety regulation in the implementation phase after the legislation of the Act on final disposal. The field of the R&D covers geological environment, engineering of geological disposal and performance assessment. As to the two underground laboratories (URLs), surface-based investigations have been carried out and the constructions of both have already started. On the basis of these investigations, geologic environmental models have been developed. The study on natural phenomena such as volcanism and faulting has been conducted. In the above ground research facilities, the development of advanced models, databases for the long-term evolution of the near-field and engineering technologies has been carried out. In terms of safety assessment methodologies, development of relevant databases and advanced safety assessment models and techniques has been carried out. The H17 report will be published in autumn 2005 for the studies conducted in the surface-based investigation phase at the URLs.

Research and development on reduced-moderation light water reactor with passive safety features (Contract research)

Iwamura, Takamichi; Okubo, Tsutomu; Akie, Hiroshi; Kugo, Teruhiko; Yonomoto, Taisuke; Kureta, Masatoshi; Ishikawa, Nobuyuki; Nagaya, Yasunobu; Araya, Fumimasa; Okajima, Shigeaki; et al.

JAERI-Research 2004-008, 383 Pages, 2004/06

JAERI-Research-2004-008.pdf:21.49MB

The present report contains the achievement of "Research and Development on Reduced-Moderation Light Water Reactor with Passive Safety Features", which was performed by Japan Atomic Energy Research Institute (JAERI), Hitachi Ltd., Japan Atomic Power Company and Tokyo Institute of Technology in FY2000-2002 as the innovative and viable nuclear energy technology (IVNET) development project operated by the Institute of Applied Energy (IAE). In the present project, the reduced-moderation water reactor (RMWR) has been developed to ensure sustainable energy supply and to solve the recent problems of nuclear power and nuclear fuel cycle, such as economical competitiveness, effective use of plutonium and reduction of spent fuel storage. The RMWR can attain the favorable characteristics such as high burnup, long operation cycle, multiple recycling of plutonium (Pu) and effective utilization of uranium resources based on accumulated LWR technologies.

Conceptual design of next generation MTR

Nagata, Hiroshi; Yamaura, Takayuki; Naka, Michihiro; Kawamata, Kazuo; Izumo, Hironobu; Hori, Naohiko; Nagao, Yoshiharu; Kusunoki, Tsuyoshi; Kaminaga, Masanori; Komori, Yoshihiro; et al.

no journal, , 

Conceptual design of the high-performance and low-cost next generation materials testing reactor which will be assumed to introduce to the nuclear power plant introduction country started from 2010 in the JAEA. Japanese atomic energy-related companies participate in this project, and this activity role as the environmental management and nuclear human resource development for the new research reactor designs. 10 MW thermal power by plate type fuel elements and swimming pool type was assumed as a design base. High safety, high cost performance, high reactor operation rate, high technology irradiation are targets of this conceptual design.

Efficient production of recombinant protease and cellulase by , expression system while difficult by

Onishi, Hiromasa*; Mizukami, Makoto*; Hanagata, Hiroshi*; Tokunaga, Masao*; Kuroki, Ryota; Adachi, Motoyasu; Ishikawa, Kazuhiko*; Miyauchi, Akira*

no journal, , 

is one of the remarkable host developing to produce secretory proteins. The proteins above amount of 10g/L have been expressed into the medium using the Brevibacillus expression system as known examples. In addition, there are many examples of expression of proteins derived from bacteria to human proteins and including disulfide bridge. Recently, we succeeded in high-level and secretory expression of protease and cellulase which are not efficiently produced in E. coli expression system.

Study of method of measurement of the -ray 3mm dose equivalent and protection measures of the lens of eyes, 1; Ionization chamber

Takimoto, Misaki; Yamazaki, Takumi; Imahashi, Atsushi; Hoshi, Katsuya; Kawasaki, Takashi; Yoshida, Tadayoshi; Takada, Chie; Tsujimura, Norio; Okada, Kazuhiko; Ishikawa, Hisashi

no journal, , 

no abstracts in English

Development of mechanical cutting technology for FBR fuel disassembly; Research of stable cutting condition for the mechanical cutting technology

Kuroda, Kazuhiko*; Kitagaki, Toru; Higuchi, Hidetoshi; Tasaka, Masayuki*; Washiya, Tadahiro; Toya, Yuichi*; Nishikawa, Hideaki*; Karatsu, Fumiaki*

no journal, , 

no abstracts in English

Development of efficient dissolution technology for FBR MOX fuel, 9; Endurance test of the bearing for rotary dram type continuous dissolver

Katsurai, Kiyomichi; Washiya, Tadahiro; Onishi, Hiroyuki*; Kuroda, Kazuhiko*; Nishikawa, Hideaki*; Nakatani, Tatsuya*; Yamashita, Kazuhiko*; Yoshimine, Chihiro*

no journal, , 

This report presents the knowledge acquired by the endurance test of the bearing used for the rotary drum type continuation dissolver under development as part of Fast Breeder Reactor Cycle technology Development Project (FaCT project). The bearing used for a dissolver is used on high radiation environment and the severe conditions of high load low swing motion operation. In order to check the endurance of the bearing in such conditions, the endurance test of the small scale of hybrid roll bearing using the lubricant which imitated carbon slide bearing as a-less lubricous type, and imitated radiation and heat degradation as a lubricous type was carried out, and the applicability to dissolver bearing was evaluated.