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Arai, Yosuke*; Kuroda, Kenta*; Nomoto, Takuya*; Tin, Z. H.*; Sakuragi, Shunsuke*; Bareille, C.*; Akebi, Shuntaro*; Kurokawa, Kifu*; Kinoshita, Yuto*; Zhang, W.-L.*; et al.
Nature Materials, 21(4), p.410 - 415, 2022/04
Times Cited Count：7 Percentile：77.62(Chemistry, Physical)Kuroda, Kenta*; Arai, Yosuke*; Rezaei, N.*; Kunisada, So*; Sakuragi, Shunsuke*; Alaei, M.*; Kinoshita, Yuto*; Bareille, C.*; Noguchi, Ryo*; Nakayama, Mitsuhiro*; et al.
Nature Communications (Internet), 11, p.2888_1 - 2888_9, 2020/06
Times Cited Count：20 Percentile：75.49(Multidisciplinary Sciences)Kuroda, Kenta*; Ochi, Masayuki*; Suzuki, Hiroyuki*; Hirayama, Motoaki*; Nakayama, Mitsuhiro*; Noguchi, Ryo*; Bareille, C.*; Akebi, Shuntaro*; Kunisada, So*; Muro, Takayuki*; et al.
Physical Review Letters, 120(8), p.086402_1 - 086402_6, 2018/02
Times Cited Count：50 Percentile：91.96(Physics, Multidisciplinary)Matsuki, Takuya; Yamanaka, Atsushi; Sekine, Megumi; Suzuki, Satoshi*; Yasuda, Takeshi; Tsutagi, Koichi; Tomikawa, Hirofumi; Nakamura, Hironobu; LaFleur, A. M.*; Browne, M. C.*
Proceedings of INMM 58th Annual Meeting (Internet), 8 Pages, 2017/07
The Tokai Reprocessing Plant (TRP) has been developing a new detector from 2015 to 2017 for purpose to monitor Pu amount in High Active Liquid Waste (HALW) containing FP. It can make a contribution to an advanced approach to effectively and efficiently conduct safeguards for reprocessing facilities because it becomes available to monitor and verify nuclear material movement continuously by a new detector, which has proposed by IAEA. For the second step of this project, we conducted dose rate measurement on the guide rail installing in the cell storing the HALW tank and comparison between measured dose rate distribution and calculation result by MCNP simulation in order to investigate the dose rate distribution which is needed for shielding design of a new detector that is used for radiation (neutron/
spectrum) measurement in the cell and inquest on the monitoring position of the detector for Pu monitoring. In this paper, we report the result of the dose rate measurement in the cell, improvement of the simulation model which is cleared by comparison between measurement result and calculation result and our future plan.
Sekine, Megumi; Matsuki, Takuya; Suzuki, Satoshi; Tanigawa, Masafumi; Yasuda, Takeshi; Yamanaka, Atsushi; Tsutagi, Koichi; Nakamura, Hironobu; Tomikawa, Hirofumi; LaFleur, A. M.*; et al.
EUR-28795-EN (Internet), p.788 - 796, 2017/00
The IAEA has proposed in its long-term R&D plan, the development of technology to enable real-time flow measurement of nuclear material as a part of an advanced approach to effective and efficient safeguards for reprocessing facilities. To address this, JAEA has designed and developed a neutron coincidence based nondestructive assay system to monitor Pu directly in solutions which is after purification process and contains very little fission products (FPs). A new detector to enable monitoring of Pu in solutions with numerous FPs is being developed as a joint research program with U.S. DOE at the High Active Liquid Waste (HALW) Storage Facility in Tokai Reprocessing Plant. As the first step, the design information of HALW tank was investigated and samples of HALW was taken and analyzed for Pu concentration and isotope composition, density, content of dominant nuclides emitting ray or neutron, etc. in order to develop a Monte Carlo N-Particle Transport Code (MCNP) of the HALW tank. In addition, ray source spectra simulated by Particle and Heavy Ion Transport code System (PHITS) was developed by extracting peaks from the analysis data with germanium detector. These outputs are used for the fundamental data in the MCNP model which is then used to evaluate the type of detector, shielding design and measurement positions. In order to evaluate available radiations to measure outside the cell wall, continuous ray and neutron measurement were carried out and the results were compared to the simulation results. The measurement results showed that there are no FP peaks above 3 MeV. This paper presents an overview of the research plan, characteristics of HALW, development of source term for MCNP, simulation of radiation dose from the HALW tank and radiation measurement results at outside of cell wall.
Suzuki, Mitsutoshi; Izumi, Yoshinori; Kimoto, Toru; Naoi, Yosuke; Inoue, Takeshi; Hoffheins, B.
IAEA-CN-184/64 (Internet), 8 Pages, 2010/11
In support of the 3S initiative, Japan Atomic Energy Agency (JAEA) has been conducting detailed analyses of the R&D programs and cultures of each of the S areas to identify overlaps where synergism and efficiencies might be realized, to determine where there are gaps in the development of a mature 3S culture, and to coordinate efforts with other Japanese and international organizations. Lessons learned in these activities can be applied to developing more efficient and effective 3S infrastructures for incorporating into Safeguards by Design methodologies. In this presentation, a risk-informed approach regarding integration of 3S will be introduced. An initial examination of incident probability and postulated consequence analyses, which are tools familiar to the nuclear safety culture, will be applied to predict and evaluate inherent uncertainties of proliferation and security risks.
Sato, Yoshihiko*; Okada, Ken*; Akiyoshi, Miyako*; Matsunaga, Takehiro*; Suzuki, Tatsuya*; Koyama, Shinichi; Ozawa, Masaki
Proceedings of International Conference on Advanced Nuclear Fuel Cycle; Sustainable Options & Industrial Perspectives (Global 2009) (CD-ROM), p.962 - 969, 2009/09
The fundamental thermochemical properties of tertiary pyridine resin (TPR) and its mixtures with methanol/HCl and HNO
were investigated and heating tests on gram scale with TPR/methanol/HNO were carried out. It was found that TPR with HCl was thermally stable. Evident thermal decomposition peaks were identified with TPR in the presence of concentrated HNO. No specific effect was observed for methanol involving. However, it was considered that the rapidly exothermic reaction can be controlled by heating temperature.
Murakami, Tatsutoshi; Suzuki, Kiichi; Hatanaka, Nobuhiro; Hanawa, Yukio; Shinozaki, Masaru; Murakami, Shinichi; Tobita, Yoshimasa; Kawasaki, Takeshi; Kobayashi, Yoshihito; Iimura, Naoto; et al.
JAEA-Technology 2008-017, 97 Pages, 2008/03
JAEA-Technology-2008-017.pdf:2.76MB
Low density MOX pellets for FBR "MONJU" have not been fabricated in Plutonium Fuel Fabricating Facility (PFPF) for these 9 years since completion of the first reload fuel for "MONJU" in 1995. In this period, about 60 % of machines in the pellet fabrication process of PFPF have been replaced with new ones, and fabrication of MOX pellets for "JOYO" has been continued using these machines. Concerning the feed MOX powders for "MONJU", the amount of decay heat has been increased with increase of accumulated Am-241 in this period. In addition, powder characteristic of recycled MOX powder which is one of feed powders, MH-MOX powder, UO
powder and recycled MOX powder, was significantly changed by replacing former processing machine used for scrap recycling with improved one. Using MOX powder with increased decay heat and recycled MOX powder processed by new machine, a series of low density MOX pellet fabrication tests were conducted to confirm pellet fabrication conditions for current pellet fabrication machines from October in 2004 to August in 2006. As a conclusion, it was confirmed that low density MOX pellets could be fabricated using these feed powders and replaced machines by adjusting pellet fabrication conditions adequately. This report summarizes the results of a series of low density MOX pellet fabrication tests.
Uchiyama, Gunzo; Watanabe, Kazuo; Miyauchi, Masakatsu; Togashi, Yoshihiro; Nakahara, Yoshinori; Fukaya, Hiroyuki; Inagawa, Jun; Suzuki, Daisuke; Sonoda, Takashi; Kono, Nobuaki; et al.
Journal of Radiation Research, 42(Suppl.), p.S11 - S16, 2001/10
no abstracts in English
Ouchi, Jin; ; Kawamura, Kazuhiro; *; ; Sasage, Kenichi; Odakura, Makoto
PNC TN8410 97-044, 53 Pages, 1997/03
The glass transition temperature of simulated waste glass was measured by DTA installed in CPF (Chemical Processing Facility) and HTS (High Level Waste Technology Section). This measurement was intended to confirm the agreement between hot and cold data as a part of characterization of high level waste glass. Glass transition temperature is an index of the temperature to keep thermal stability of high-level waste glass. Since devitrification deteriorates characteristics of waste glass above glass transition temperature, it is necessary to measure glass transition temperature and keep glass temperature below glass transition temperature. The conventional method to determine glass transition temperature is the measurement of thermal expansion, but DTA is adopted for radioactive sample because of easier preparation. We obtained following results by measuring glass transition temperature of simulated waste glasses after calibration with standard specimen : (1)The average glass transition temperature of TVF waste glass (P0798) measured by DTA in HTS and CPF was 494
C (standard deviation 3 
: 8.2C) and 495C (3: 1.8C), respectively. The difference between two analyzer was 1C. It shows the good agreement between hot and cold DTA data. (2)Glass transition temperature of P0798 measured by thermal expansion method was 495C(3: 8.1C) and it agrees well with that measured by DTA. (3)The average glass transition temperature of simulated highly waste-loading glass (P1102) measured by DTA in HTS and CPF was 510.5 
2.5C.
laserIkezoe, Yasumasa; Soga, Takeshi; Suzuki, Kazuya; Ono, Shinichi*
Journal of the Mass Spectometry Society of Japan, 43(5), p.257 - 263, 1995/00
no abstracts in English
; ; ; ; ; Kano, Yutaka; Yoshida, Mika
PNC TN8440 94-003, 157 Pages, 1994/03
Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed since 1975, based on "Safety Regulations for the Tokai Reprocessing Plant, Chapter VII - Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitants due to the radioactivity discharged from the plant during 1993. Appendices present comprehensive information, such as monitoring program, monitoring results, meteorological data and annual discharges from the plant.
; ; ; ; ; Sumiya, Shuichi; ; Yoshida, Mika; ; Isozaki, Tokuju; et al.
PNC TN8440 93-027, 85 Pages, 1993/08
None
; ; ; ; Kano, Yutaka; Yoshida, Mika;
PNC TN8440 93-006, 157 Pages, 1993/03
Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed since 1975, based on "Safety Regulations for the Tokai Reprocessing Plant, Chapter VII - Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitants due to the radioactivity discharged from the plant during 1992. Appendices present comprehensive information, such as monitoring program, monitoring results, meteorological data and annual discharges from the plant.
laser photolysis of clustered ions, IIkezoe, Yasumasa; Soga, Takeshi; Suzuki, Kazuya; Ono, Shinichi
JAERI-M 90-141, 55 Pages, 1990/09
no abstracts in English
Shibata, Takemasa; *; ; *; *; Arisawa, Takashi
Shinku, 31(5), p.559 - 561, 1988/00
no abstracts in English
*; *; *; *; *; ; *; Yamamoto, Kazuya*
PNC TN841 85-25, 125 Pages, 1985/03
no abstracts in English
