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Kumada, Takayuki; Motokawa, Ryuhei; Oba, Yojiro; Nakagawa, Hiroshi; Sekine, Yurina; Micheau, C.; Ueda, Yuki; Sugita, Tsuyoshi; Birumachi, Atsushi; Sasaki, Miki; et al.
Journal of Applied Crystallography, 56(6), p.1776 - 1783, 2023/12
Times Cited Count：1 Percentile：65.66(Chemistry, Multidisciplinary)The combination of the existing position-sensitive photomultiplier and the 3He main detector with focusing devices, and the newly installed front detectors in SANS-J at JRR-3 covers small-angle neutron scattering signals in the range of the magnitude of the scattering vector Q from 0.002 to 6 nm-1 gaplessly with three standard device layouts. The installation of the front detector and a graphical user interface system largely improved the usability of SANS-J.
Tsuchiya, Kunihiko
Nihon Genshiryoku Gakkai-Shi ATOMO
, 65(6), p.393 - 397, 2023/06
no abstracts in English
Okada, Shota; Murakami, Masashi; Kochiyama, Mami; Izumo, Sari; Sakai, Akihiro
JAEA-Testing 2022-002, 66 Pages, 2022/08
JAEA-Testing-2022-002.pdf:2.46MB
Japan Atomic Energy Agency is an implementing organization of burial disposal for low-level radioactive waste generated from research, industrial and medical facilities in Japan. Radioactivity concentrations of the waste are essential information for design of the disposal facility and for licensing process. A lot of the waste subjected to the burial disposal is arising from dismantling of nuclear facilities. Radioactive Wastes Disposal enter has therefore discussed a procedure to evaluate the radioactivity concentrations by theoretical calculation for waste arising from the dismantling of the research reactors facilities and summarized the common procedure. The procedure includes evaluation of radioactive inventory by activation calculation, validation of the calculation results, and determination of the disposal classification as well as organization of the data on total radioactivity and maximum radioactivity concentration for each classification. For the evaluation of radioactive inventory, neutron flux and energy spectra are calculated at each region in the reactor facility using two- or three-dimensional neutron transport code. The activation calculation is then conducted for 140 nuclides using the results of neutron transport calculation and an activation calculation code. The recommended codes in this report for neutron transport calculation are two-dimensional discrete ordinate code DORT, three-dimensional discrete ordinate code TORT, or Monte Carlo codes MCNP and PHITS, and for activation calculation is ORIGEN-S. Other recommendation of cross-section libraries and calculation conditions are also indicated in this report. In the course of the establishment of the procedure, Radioactive Wastes Disposal Center has discussed the commonly available procedure at meetings. It has periodically held to exchange information with external operators which have research reactor facilities. The procedure will properly be reviewed and be revised by reflecting future situ
Endo, Akira
Isotope News, (781), P. 3, 2022/06
The research reactor JRR-3 at the Nuclear Science Research Institute of Japan Atomic Energy Agency resumed its operation in February 2021 for the first time in 10 years. After commissioning, neutron beam experimental apparatus and irradiation facilities were used from July to November, and the operation in 2021 was completed as planned. During this period, Ir-192 and Au-198 were produced and supplied for therapeutic use, and test irradiation for the production of Mo-99 was performed. This is resumption of radioisotope production using nuclear reactors in Japan, which had stopped after the Great East Japan Earthquake. This article introduces future efforts of radioisotope production for medical applications in JRR-3.
Endo, Akira
Hokeikyo Nyusu, (68), P. 1, 2021/10
This article introduces resumption of utilization of the research reactor JRR-3 at the Nuclear Science Research Institute, JAEA. JRR-3 resumed its operation in July 2021 for the first time in 10 years and 7 months, after the confirmation of its conformity to the new regulatory requirements established by the Nuclear Regulatory Commission following the accident at the TEPCO's Fukushima Daiichi Nuclear Power Plant in March 2011. JRR-3 is expected to produce many research results in academic and industrial applications as a research center for neutron science in collaboration with the Materials and Life Science Facility (MFL) of the Japan Proton Accelerator Research Complex (J-PARC).
Am(n,
)
Am, 
Am reactionsNakamura, Shoji; Endo, Shunsuke; Kimura, Atsushi; Shibahara, Yuji*
KURNS Progress Report 2019, P. 132, 2020/08
Research and development were made for accuracy improvement of neutron capture cross section data on Am among minor actinides. First, the emission probabilities of decay rays were obtained with high accuracy, and the amount of the ground state of 
Am produced by reactor neutron irradiation of Am was examinded by -ray measurement. Next, the total amount of isomer and ground states was examoned by 
-ray measurement.
Takeda, Masayasu
Hamon, 30(1), p.7 - 8, 2020/02
Safety review of JRR-3 under the New Regulatory Requirements was completed on 7th November 2018. Neutron beam will come back in early 2021 after reinforcement works of the roof of the reactor building, the peripheral structures like a stack, a cooling tower, and the experimental hall. The future of neutron sciences using the research reactor strongly depends on how many impacted researches using JRR-3 are achieved after restarting JRR-3. At this stage, we can learn a lot of things from the back numbers of HAMON.
Matsue, Hideaki
Hoshasen (Internet), 45(2), p.77 - 88, 2019/07
JRR-3 operated by Japan Atomic Energy Agency (JAEA) is 20 MW grade research reactor for widely used for various academic research and industrial applications in many fields from utilization of internal irradiation to utilization of neutron beam. Although JRR-3 has not been operated due to respond to the new regulation standard established after the Great East Japan Earthquake of March 11, 2011, JRR-3 will resume operation in October 2020. This article reports neutron utilization such as various kinds of reactor irradiation, prompt gamma-ray analysis, neutron radiography and neutron residual stress analysis, and the efforts of the JRR-3 user 's office aiming for a one - stop office.
Murakami, Masashi; Hoshino, Yuzuru; Nakatani, Takayoshi; Sugaya, Toshikatsu; Fukumura, Nobuo*; Sanda, Toshio*; Sakai, Akihiro
JAEA-Technology 2019-003, 50 Pages, 2019/06
JAEA-Technology-2019-003.pdf:4.42MB
Toward the establishment of a common approach to determine the radioactivity concentrations in dismantling wastes arising from research reactors, radionuclide concentrations in the reactor structure materials of aluminum, carbon steel, shield concrete, and graphite of TRIGA Mark II reactor at Rikkyo University, Japan, were evaluated with both radiochemical analysis and theoretical calculation. The measured nuclides by the radiochemical analysis were 
H, 
Co, and 
Ni in aluminum, H, Co, Ni, and 
Eu in carbon steel, H, Co, and Eu in shield concrete, and H, 
C, Co, Ni, and Eu in graphite. Neutron-flux distributions and neutron-induced activities were computed with DORT and ORIGEN-ARP codes, respectively. Using the results of material composition analysis, radioactivity concentrations were conservatively predicted with good accuracy except for graphite material.
Tsuchiya, Kunihiko; Nagao, Yoshiharu
Kinzoku, 86(10), p.893 - 899, 2016/10
no abstracts in English
Takeda, Masayasu; Matsubayashi, Masahito
Nihon Genshiryoku Gakkai-Shi ATOMO, 58(6), p.371 - 375, 2016/06
no abstracts in English
Kurosawa, Ryohei; Okada, Shota; Sakai, Akihiro; Nakata, Hisakazu; Amazawa, Hiroya
JAEA-Data/Code 2015-005, 82 Pages, 2015/06
JAEA-Data-Code-2015-005.pdf:3.47MB
The calculation tool of neutron flux at materials within and around the research reactor was developed so that the user more easily evaluate radioactivity inventory in radioactive waste generated from the decommissioning of research reactors at various conditions. The tool consists of some computer programs which calculate macroscopic effective cross section at materials, calculate the neutron flux at materials within and around the research reactor, and edit the neutron flux to evaluate the radioactive inventory. This report describes the outline of evaluation method of neutron flux at materials within and around the research reactor, the structure and functions of the calculation tool of neutron flux, input and output data, and sample run with the tool.
Kawamura, Hiroshi
Gakujutsu No Doko, 20(6), p.32 - 38, 2015/06
no abstracts in English
Kawamura, Hiroshi
Denki Hyoron, 100(5), p.11 - 12, 2015/05
no abstracts in English
Kakurai, Kazuhisa; Endo, Yasuo
Kotai Butsuri, 40(4), p.239 - 250, 2005/04
no abstracts in English
Morii, Yukio; Isshiki, Masahiko
Kessho Kaiseki Handobukku, p.111 - 114, 1999/09
no abstracts in English
Yonezawa, Chushiro
Radioisotopes, 46(6), p.74 - 81, 1997/06
no abstracts in English
Morii, Yukio; Isshiki, Masahiko
Radioisotopes, 45(11), p.717 - 721, 1996/11
no abstracts in English
Matsubayashi, Masahito
Chuseishi Rajiogurafi Shashinshu, P. 112, 1995/11
no abstracts in English
Tsuji, Hirokazu; Miya, Kenzo*
Nucl. Eng. Des., 155, p.527 - 546, 1995/00
Times Cited Count：1 Percentile：16.76(Nuclear Science & Technology)no abstracts in English
