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Sakasegawa, Hideo; Nomura, Mitsuo; Sawayama, Kengo; Nakayama, Takuya; Yaita, Yumi*; Yonekawa, Hitoshi*; Kobayashi, Noboru*; Arima, Tatsumi*; Hiyama, Toshiaki*; Murata, Eiichi*
Progress in Nuclear Energy, 153, p.104396_1 - 104396_9, 2022/11
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)When dismantling centrifuges in uranium-enrichment facilities, decontamination techniques must be developed to remove uranium-contaminated surfaces of dismantled parts selectively. Dismantled uranium-contaminated parts can be disposed of as nonradioactive wastes or recycled after decontamination appropriate for clearance. previously, we developed a liquid decontamination technique using acidic electrolyzed water to remove uranium-contaminated surfaces. However, further developments are still needed for its actual application. Dismantled parts have various uranium-contaminated surface features due to varied operational conditions, inhomogeneous decontamination using iodine heptafluoride gas, and changes in long-term storage conditions after dismantling. Here, we performed liquid decontamination on specimens with varying uranium-contaminated surfaces cut from a centrifuge made of low-carbon steel. From the results, the liquid decontamination can effectively remove the uranium-contaminated surfaces, and radioactive concentrations fell below the target value within twenty minutes. Although the required time should also depend on dismantled parts' sizes and shapes in their actual application, we demonstrated that it could be an effective decontamination technique for uranium-contaminated steels of dismantled centrifuges.
Tachibana, Mitsuo; Murata, Masato; Tasaki, Tadayuki; Usui, Hideo; Kubota, Shintaro
Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.1987 - 1996, 2015/09
230 various types of nuclear facilities were constructed in JAEA's R&D Institutes or Center until the establishment of the JAEA in 2005. The JAEA has efficiently and systematically decommissioned nuclear facilities that would no longer be required after the establishment of the JAEA. Decommissioning of nuclear facilities in each JAEA's R&D Institutes or Center was continued based on the second midterm plan of the JAEA from FY2010 to FY2014. Decommissioning of 2 nuclear facilities was completed during the second midterm. This report describes current status of decommissioning activities in the JAEA during the second midterm and outline of the decommissioning plan in the third midterm.
Kishida, Norio*; Murata, Toru*; Asami, Tetsuo*; Kosako, Kazuaki*; Maki, Koichi*; Harada, Hideo*; Lee, Y.*; Chang, J.*; Chiba, Satoshi; Fukahori, Tokio
AIP Conference Proceedings 769, p.199 - 202, 2005/05
Nuclear data for photonuclear reactions are required in the field of shielding design of high-energy electron accelerators and high-energy 
-ray therapy. The JENDL Photonuclear Data File was prepared by a working group on nuclear data evaluations for photonuclear reactions in Japanese Nuclear Data Committee. From a survey of many literatures, it is difficult to construct the photonuclear data file by using only measured data, since there are not sufficient experimental data. We were therefore evaluating with theoretical calculations based on statistical nuclear reaction models. The photonuclear cross sections that are to be contained in the file are as follows: photoabsorption cross sections, yield cross sections and DDX for neutrons, protons, deuterons, tritons, 
He-particles and alpha-particles, and isotope production cross sections. For the actinide nuclides, photofission cross sections are also included. The maximum energy of incident photons is 140 MeV and stored are the photonuclear data for 68 nuclides from 
H to 
Np.
Shibata, Keiichi; Kawano, Toshihiko*; Nakagawa, Tsuneo; Iwamoto, Osamu; Katakura, Junichi; Fukahori, Tokio; Chiba, Satoshi; Hasegawa, Akira; Murata, Toru*; Matsunobu, Hiroyuki*; et al.
Journal of Nuclear Science and Technology, 39(11), p.1125 - 1136, 2002/11
Times Cited Count：669 Percentile：96.97(Nuclear Science & Technology)Evaluation for JENDL-3.3 has been performed by considering the accumulated feedback information and various benchmark tests of the previous library JENDL-3.2. The major problems of the JENDL-3.2 data were solved by the new library: overestimation of criticality values for thermal fission reactors was improved by the modifications of fission cross sections and fission neutron spectra for 
U; incorrect energy distributions of secondary neutrons from important heavy nuclides were replaced with statistical model calculations; the inconsistency between elemental and isotopic evaluations was removed for medium-heavy nuclides. Moreover, covariance data were provided for 20 nuclides. The reliability of JENDL-3.3 was investigated by the benchmark analyses on reactor and shielding performances. The results of the analyses indicate that JENDL-3.3 predicts various reactor and shielding characteristics better than JENDL-3.2.
; Kumamaru, Hiroshige; Murata, Hideo; Kukita, Yutaka
JAERI-Research 96-038, 55 Pages, 1996/07
JAERI-Research-96-038.pdf:1.63MB
no abstracts in English
Anoda, Yoshinari; *; ; Murata, Hideo
JAERI-Tech 96-028, 71 Pages, 1996/06
no abstracts in English
Kumamaru, Hiroshige; ; Murata, Hideo; Kukita, Yutaka; Akiyama, Mamoru*; *; *; *; *; *; et al.
Proc. of ASME
JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 1(PART B), p.669 - 674, 1996/00
no abstracts in English
Kumamaru, Hiroshige; Murata, Hideo; ; Kukita, Yutaka
The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 1, 0, p.217 - 222, 1995/00
no abstracts in English
Kumamaru, Hiroshige; ; Murata, Hideo; Kukita, Yutaka
Nucl. Eng. Des., 150, p.95 - 105, 1994/00
Times Cited Count：35 Percentile：92.13(Nuclear Science & Technology)no abstracts in English
*; *; Haga, Katsuhiro*; Anoda, Yoshinari; Murata, Hideo; Kukita, Yutaka
Proc. of the 4th Int. Topical Meeting on Nuclear Thermal Hydraulics,Operations and Safety,Vol. 2, 0, p.38.A.1 - 38.A.6, 1994/00
no abstracts in English
; Kumamaru, Hiroshige; Murata, Hideo; Anoda, Yoshinari; Kukita, Yutaka
JAERI-M 93-200, 56 Pages, 1993/10
no abstracts in English
*; Haga, Katsuhiro*; *; Murata, Hideo; Anoda, Yoshinari; Kukita, Yutaka
Proc. of the 2nd ASME/JSME Nuclear Engineering, p.301 - 306, 1993/00
no abstracts in English
*; *; *; *; Anoda, Yoshinari; Murata, Hideo; Kukita, Yutaka
Journal of Nuclear Science and Technology, 29(12), p.1152 - 1161, 1992/12
no abstracts in English
Nakamura, Hideo; Murata, Hideo; Ito, Hideo; Anoda, Yoshinari; Kumamaru, Hiroshige; Kukita, Yutaka
Kashika Joho Gakkai-Shi, 12(47), p.47 - 56, 1992/10
no abstracts in English
Murata, Hideo; *
Nihon Kikai Gakkai Rombunshu, B, 58(550), p.1912 - 1917, 1992/06
no abstracts in English
*; *; *; I.D.Irianto*; *; *; Anoda, Yoshinari; Murata, Hideo; Kukita, Yutaka
Proc. of the Int. Conf. on Design and Safety of Advanced Nuclear Power Plants,Vol. 2, p.17.6-1 - 17.6-6, 1992/00
no abstracts in English
Kumamaru, Hiroshige; Suzuki, Mitsuhiro; Anoda, Yoshinari; Nakamura, Hideo; Yonomoto, Taisuke; Murata, Hideo
JAERI-M 91-167, 293 Pages, 1991/10
no abstracts in English
Suzuki, Mitsuhiro; Nakamura, Hideo; Yonomoto, Taisuke; Kumamaru, Hiroshige; Anoda, Yoshinari; Murata, Hideo
JAERI-M 91-103, 156 Pages, 1991/07
no abstracts in English
*; Anoda, Yoshinari; Murata, Hideo; Yonomoto, Taisuke; *; Kukita, Yutaka
JAERI-M 91-076, 34 Pages, 1991/05
no abstracts in English
Nakamura, Hideo; Murata, Hideo; Ito, Hideo; Anoda, Yoshinari; Kumamaru, Hiroshige; Kukita, Yutaka
ANS Proc. 1991 National Heat Transfer Conf., Vol. 5, p.175 - 180, 1991/00
no abstracts in English
