Electron-tracking Compton camera imaging of technetium-95m

Hatsukawa, Yuichi*; Hayakawa, Takehito*; Tsukada, Kazuaki; Hashimoto, Kazuyuki*; Sato, Tetsuya; Asai, Masato; Toyoshima, Atsushi; Tanimori, Toru*; Sonoda, Shinya*; Kabuki, Shigeto*; et al.

PLOS ONE (Internet), 13(12), p.e0208909_1 - e0208909_12, 2018/12

AA2018-0639.pdf:2.39MB

https://doi.org/10.1371/journal.pone.0208909

Imaging of Tc radioisotope was conducted using an electron tracking-Compton camera (ETCC). Tc emits 204, 582, and 835 keV rays, and was produced in the Mo(p,n)Tc reaction with a Mo-enriched target. The recycling of the Mo-enriched molybdenum trioxide was investigated, and the recycled yield of Mo was achieved to be 70% - 90%. The images were obtained with each of the three rays. Results showed that the spatial resolution increases with increasing -ray energy, and suggested that the ETCC with high-energy -ray emitters such as Tc is useful for the medical imaging of deep tissue and organs in the human body.

Feasibility Study on Commercialization of Fast Breeder Reactor Cycle Systems, Interim Report of Phase2 -Technical Study Report for Nuclear Fuel Cycle Systems-

Sato, Koji; Koma, Yoshikazu; Inoue, Akira; Yonezawa, Shigeaki; Takata, Takeshi; Nakabayashi, Hiroki; Namekawa, Takashi; Kawaguchi, Koichi

JNC TN9400 2004-036, 1051 Pages, 2004/06

JNC-TN9400-2004-036.pdf:90.95MB

The plant concept concerning the fuel cycle systems (combination of the reprocessing and the fuel fabrication )has been constructed to reduce their total cost by the introduction of various innovative techniques and to apply their utmost superior efficiency from such standpoints of a decrease in the environmental burden, better resource utilization and proliferation resistance improvement by the low decontamination transuranium element (TRU) recycle. For economical efficiency, less than 0.8 yen/kWh which is the demand value (total of the reprocessing expense and the fuel fabrication expense) of the fuel cycle expense satisfied each combination case at 200 tHM/y scale provisionally set for large-scale facilities. On the other hand, the combination case with a low breeder reactor core has satisfied the demand value, with improvement of the average burnup by the radial direction blanket fuel deletion contributing to the decrease of the fuel cycle expense at 50 tHM/y scale provisionally set for small-scale facilities.

TECHNICAL STUDY REPORT ON REPROCESSING SYSTEMS, Investigation on Alternatives for Advanced Aqueous Reprocessing System

Koma, Yoshikazu; Takata, Takeshi; Kamiya, Masayoshi; Sato, Koji

JNC TN9410 2003-010, 112 Pages, 2003/12

JNC-TN9410-2003-010.pdf:4.73MB

This report summarizes the design work made bay the reprocessing Technoplogy Group in 2002 FYJ and includes the followings: advanced aqueous reprocesing, supercritical liquid direct extraction as an alternative, Am and Cm recovery and FP recovery.

Design Study on Minor Actinides Recovery for the NEXT Reprocessing

Koma, Yoshikazu; Takata, Takeshi; Sato, Koji; Sato, Koji

Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), p.1939 - 1944, 2003/00

As a part of the fasibility study on commercialized fast cycle systems,conceptual design study on aqueous recovery process of Am and Cm was conducted in order to choose the most promising method for future reprocessing plant. Process flow diagram,material balance and arrangement of equipment were made for the three alternative methods. The SETFICS is a solvent extraction using TRUEX solvent and DTPA-nitrate solution to obtain actinides (III) products wothout laight lanthanides. The MAREC is an extraction chromatography using a porous silica support. Amine extraction combines oxdation of actinides(III) to (IV) and extractionof polyanionic actinides(IV) complex into amine mixed solvent.Definite difference was not found in technical feasibility and safety of them at the present.Comparing waste generation and cost for apparatus, the MAREC process seems to have an advantage.

ICONE-8 participation and investigation report of dry process in Argonne National Laboratory (ANL), USA

; Washiya, Tadahiro;

JNC TN8420 2001-009, 48 Pages, 2000/04

JNC-TN8420-2001-009.pdf:0.58MB

ICONE(International Conference on Nuclear Engineering) is an international conference on nuclear chemical engineering held among the United States, Japan and Europe, and ICONE8 (the 8th time of the conference) was held at Baltimore, USA on April 2 to 6, 2000. The authors of this paper reported the latest information on the reprocessing technology in the following session of the conference and audited the panel discussion and the technical report of the dry reprocessing technology etc. in the conference. (1)Investigation of Safety Evaluation Method and Application to Tokai Reprocessing Plant (TRP) in session of Track-5 "Non-reactor Safety and Reliability" (Nakamura) (2)Structural Improvement on the continuous rotary dissolver in session of Track-9 "Spent Nuclear Fuel and Waste Processing" (Washiya) (3)Development of Evaporators Made of Ti-5% Ta Alloy and Zr - Endurance Test By Mock-Up unit" in session of Track-2 "Aging and Modeling of Component Aging, Including corrosion of Metals and Welds.. passivation, and passive films" (Takata) At the conference, about 650 people participated from the United States, Japan, France, Canada and others, about700 research announcements, 7 keynote lecture and 8 panel discussion were done, flourishing with many participants. Moreover, as the conference was held in the year of 2000, the evaluation of this century and the direction of the next century of nuclear energy were discussed. After the conference, authors visited Argonne National Laboratory (ANL-E, ANL-W) and exchanged information concerning dry process with researchers of ANL-E and ANL-W, visiting ANL facilities. It was very significant to be able to acquire the information on the dry process developed in ANL and realize the device scale and the development environment, etc. and acquire technical information in detail which would not be able to obtain by engineering data, exchanging information with ANL engineers directly. It is suggested to be very valuable that the ...

Research and development project on irradiation damage management technology for structural materials of long-life nuclear plant, 6; Evalaution of irradiation damage indicators due to reactor neutron irradiation and cyclotron helium implantation, etc

Wakai, Eiichi; Takada, Fumiki; Kato, Yoshiaki; Kato, Shoichi; Hirade, Tetsuya; Takaya, Shigeru; Matsui, Yoshinori; Fujii, Kimio; Aoto, Kazumi; Nogami, Shuhei*; et al.

no journal, , 

no abstracts in English

Effects of DPA and helium production on radiation damage microstructures and the mechanical properties in irradiated austenitic stainless steels and ferritic steel

Wakai, Eiichi; Takaya, Shigeru; Nagae, Yuji; Suzudo, Tomoaki; Hirade, Tetsuya; Matsui, Yoshinori; Nogami, Shuhei*; Hasegawa, Akira*; Abe, Hiroaki*; Iwai, Takeo*; et al.

no journal, , 

no abstracts in English