Refine your search:     
Report No.
 - 
Search Results: Records 1-8 displayed on this page of 8
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

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

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.

Journal Articles

Radioactive waste management in O-arai Research and Development Center

Maeda, Atsushi; Kowata, Koichi; Yamazaki, Yasuo; Takahashi, Kozo; Okubo, Toshiyuki; Miyazaki, Hitoshi

Dekomisshoningu Giho, (33), p.58 - 66, 2006/03

By the Japan Atomic Energy Agency (JAEA), designed decommissioning of nuclear facility and the treatment and disposal of radioactive waste will be carried out systematically and efficiently as responsibility as the installer of the nuclear power facility and generator of radioactive waste. This paper shows the present status of radioactive waste management in O-arai Research and Development Center, one of the research and development bases of JAEA. The management of low-level radioactive waste, including those accepted from outside operator of O-arai district, is carried out by the major premise of ensuring safety at O-arai Waste Management Facility. Treatment related to volume reduction and stabilization by means such as incineration and compression of solid waste, and solidification of liquid, as well as waste storage management is steadfastly promoted, so that these substances may be adequately stored and managed until they are disposed of.

JAEA Reports

Stability of Uranium Complexes in Supercritical Fluids and their Effective Recovery(The joint research report about precedence basic engineering research)

Tomiyasu, Hiroshi*; Nomura, Mitsuo; Yamazaki, Hitoshi; Hayashibara, Kenichi

JNC TY6400 2004-004, 18 Pages, 2004/07

JNC-TY6400-2004-004.pdf:0.65MB

This study has been performed to establish a method to recover uranium from uranium containing NaF and CaF2 wastes without forming any secondary wastes. For this purpose the use of supercritical carbon dioxide was primarily considered. Although TBP has been generally used with supercritical carbon dioxide to extract uranium, the use of TBP was ruled out in the present study because of the formation of secondary wastes due to phosphorous oxides. Among a variety of ligands, we have choused acetylacetone as a ligand for the extraction of uranyl ion. Acetylacetone is a strong chelate ligand, which dose not gives any solid residual after vaporization. As a matter of fact, our experimental result indicates that acetylacetone is a stronger ligand for uranyl ion compared with TBP., because uranyl TBP complex is replaced by acetylacetonate resulting in the formation of acetylaetonate complex. Experiments were carried out to recover uranium from the NaF waste by use of supercritical carbon dioxide containing acetylacetone, and it was found that uranium was only partly extracted to carbon dioxide phase. This might be attributed to the strong uranium fluoride complexes and also to the distribution of uranium to the inside of NaF pellets. In order to recover uranium from the NaF waste, another method was also carried out as follows: dissolve NaF waste by hot water, then add NaOH to the solution as to form the precipitation of uranium hydrolyzed species, where uranium can be recovered at high yield using centrifugation, and finally the addition of ethanol yields the NaF powder. In conclusion, the recovery of uranium from fluoride wastes seems to be difficult by the method using supercritical carbon dioxide; however, we have established a new method to recover both uranium and NaF in high yield.

JAEA Reports

Recovery and Reuse of Uranium from Radioactive Carbon Dioxide (The joint research report about precedence basic engineering research)

Aihara, Masahiko*; Yanai, Shinjiro*; Shimazaki, Yohei*; Nomura, Mitsuo; Yamazaki, Hitoshi; Hayashibara, Kenichi

JNC TY6400 2004-003, 93 Pages, 2004/07

JNC-TY6400-2004-003.pdf:2.19MB

To run the nuclear fuel cycle safely, new treatment and disposal technologies of radioactive waste from the cycle must be developed. Super critical CO2 extraction attracts attention as a technology to recover the uranium in low level solid waste. In this paper it is proposed that use of carbonation of calcium oxide and decarbonation of calcium carbonate for the system which recovers and reuses high pressure carbon dioxide discharge form the super-critical process. Conducting the cycle reaction experiment at the high pressure of carbon dioxide with the calcium oxide absorbent, the reaction velocity analysis, the structural analysis of solid reactant, the numerical analysis of the reaction characteristic and the recover-reuse process were discussed. The rate of carbonation at about 2MPa was most rapid with the stable reaction conversion of about 0.4 through 5 cycles. In the range of these experiment conditions The solid reactant was observed consisting of about 1-10 mm particles of the aggregate of minute grains. It was found that a blockade of the void between the grains after carbonation at high pressure CO2 caused the reduction of conversion and rate of carbonation. The heat consumption of CO2 recovery for the recover-reuse system was estimated by use of the reaction analysis data.

Oral presentation

Measurement technology for safeguards analysis at the Tokai reprocessing plant

Yamamoto, Masahiko; Surugaya, Naoki; Taguchi, Shigeo; Ishibashi, Atsushi; Horigome, Kazushi; Yamazaki, Hitoshi; Ogura, Hiroshi; Watahiki, Hiromi; Watanabe, Masahisa; Kurosawa, Akira; et al.

no journal, , 

no abstracts in English

Oral presentation

Mach-Zehnder type thermo-optic switch fabricated by proton beam writing

Ozawa, Yusuke*; Kubota, Hitoshi*; Miura, Kenta*; Hanaizumi, Osamu*; Noguchi, Katsuya*; Sato, Takahiro; Ishii, Yasuyuki; Koka, Masashi; Takano, Katsuyoshi*; Okubo, Takeru; et al.

no journal, , 

Oral presentation

The Evaluation of nuclear forensics analytical capability in the 7th Collaborative Materials Exercise of the Nuclear Forensics (CMX-7)

Matsui, Yoshiki; Kimura, Yoshiki; Umino, Yuji*; Hosoi, Masaharu*; Matsumoto, Tetsuya*; Shinohara, Nobuo; Yamazaki, Hitoshi; Yamaguchi, Tomoki

no journal, , 

The Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the Japan Atomic Energy Agency (JAEA) is developing technologies for nuclear forensics to identify the origin and intended use of nuclear and radioactive materials. In order to share the experience on nuclear forensics analysis and to improve analytical techniques in the international community, the Nuclear Forensics International Technical Working Group (ITWG) regularly holds the Collaborative Materials Exercise (CMX). The ISCN participated in the 7th exercise (CMX-7) this time. This paper reports the experience of the exercise, and discusses nuclear forensics analytical capability of the ISCN based on the review of the exercise.

Oral presentation

The Experience of the 7th Collaborative Materials Exercise of the Nuclear Forensics (CMX-7) and future tasks

Matsui, Yoshiki; Kimura, Yoshiki; Umino, Yuji*; Hosoi, Masaharu*; Matsumoto, Tetsuya*; Shinohara, Nobuo; Yamazaki, Hitoshi; Yamaguchi, Tomoki

no journal, , 

8 (Records 1-8 displayed on this page)
  • 1