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Hirano, Tatsumi*; Maeda, Takehiro*; Murata, Tetsuyuki*; Yamamoto, Takahiro*; Matsubara, Eiichiro*; Shobu, Takahisa; Shiro, Ayumi*; Yasuda, Ryo*; Takamatsu, Daiko*
SPring-8/SACLA Riyo Kenkyu Seikashu (Internet), 11(5), p.345 - 353, 2023/10
no abstracts in English
Hirano, Tatsumi*; Maeda, Takehiro*; Murata, Tetsuyuki*; Yamaki, Takahiro*; Matsubara, Eiichiro*; Shobu, Takahisa; Shiro, Ayumi*; Yasuda, Ryo*; Takamatsu, Daiko*
SPring-8/SACLA Riyo Kenkyu Seikashu (Internet), 11(1), p.49 - 57, 2023/02
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.
Nakayama, Takuya; Nomura, Mitsuo; Mita, Yutaka; Yonekawa, Hitoshi*; Bunbai, Misako*; Yaita, Yumi*; Murata, Eiichi*; Hosaka, Katsumi*; Sugitsue, Noritake
Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 8 Pages, 2019/05
Clearance of contaminated metal is important for recycling and volume reduction of radioactive waste. Among applicable decontamination technologies, immersion method with ultrasonic cleaning is considered to be effective for metal materials having various shapes. in this study is to demonstrate decontamination of carbon steel contaminated by uranium hexafluoride to the target level for clearance (less than 0.04 Bq/cm
), and minimize secondary waste. In this test, acidic electrolytic water, dilute hydrochloric acid, dilute sulfuric acid and ozone water with various pH and redox potential were used as decontamination solutions to be tested. We found that acidic electrolytic water is effective solution for decontamination of carbon steel contaminated by uranium hexafluoride. It could be decontaminate less than target level for clearance, and reduced secondary waste relatively.
Shibata, Keiichi; Iwamoto, Osamu; Nakagawa, Tsuneo*; Iwamoto, Nobuyuki; Ichihara, Akira; Kunieda, Satoshi; Chiba, Satoshi; Furutaka, Kazuyoshi; Otsuka, Naohiko*; Osawa, Takaaki*; et al.
Journal of Nuclear Science and Technology, 48(1), p.1 - 30, 2011/01
Times Cited Count：1611 Percentile：100(Nuclear Science & Technology)The fourth version of Japanese Evaluated Nuclear Data Library has been produced. In the new library, much emphasis is placed on the improvements of fission product and minor actinoid data. Two nuclear model codes were developed to evaluate the cross sections of fission products and minor actinoids. Coupled-channel optical model parameters, which can be applied to wide mass and energy regions, were obtained for nuclear model calculations. Thermal cross sections of actinoids were determined by considering recent experimental data or by the systematics of neighboring nuclei. A simultaneous evaluation was performed for the fission cross sections of important uranium and plutonium isotopes above 10 keV. The data on FP were re-evaluated, and new evaluations were performed for 30 nuclides. The data on light elements and structural materials were partly re-evaluated. The new library was released as JENDL-4.0 in May 2010.
,xn) reaction data for JENDL/AN-2005Murata, Toru*; Matsunobu, Hiroyuki*; Shibata, Keiichi
JAEA-Research 2006-052, 63 Pages, 2006/07
JAEA-Research-2006-052.pdf:5.11MB
Neutron emission data of the 
reactions were evaluated in the incident -particle energy region below 15 MeV for nuclides important mainly in nuclear fuel-cycle applications, namely, 
, 
, 
, 
, 
, 
, 
, 
, 
and 
. The evaluation was performed on the basis of available experimental data and nuclear model calculations. The evaluated nuclear data were compiled in the ENDF-6 format, and released in June 2005 as JENDL 
Reaction Data File 2005 (JENDL/AN-2005) which is one of JENDL special-purpose files. This report describes evaluation methods and the results on evalauted cross sections and angular- and energy-distributions of emitted neutrons.
Nishitani, Takeo; Ochiai, Kentaro; Maekawa, Fujio; Shibata, Keiichi; Wada, Masayuki*; Murata, Isao*
IAEA-CN-116/FT/P1-22 (CD-ROM), 8 Pages, 2004/11
no abstracts in English
Kawano, Toshihiko*; Matsunobu, Hiroyuki*; Murata, Toru*; Zukeran, Atsushi*; Nakajima, Yutaka*; Kawai, Masayoshi*; Iwamoto, Osamu; Shibata, Keiichi; Nakagawa, Tsuneo; Osawa, Takaaki*; et al.
JAERI-Research 2003-026, 53 Pages, 2003/12
JAERI-Research-2003-026.pdf:2.48MB
New evaluations of neutron nuclear data for Uranium, Plutonium, and Thorium isotopes which are essential for applications to nuclear technology were carried out for the Japanese Evaluated Nuclear Data Library, JENDL-3.3. The objectives of the current release of JENDL were to fix several problems which have been reported for the previous version, to improve the accuracy of the data, and to evaluate covariances for the important nuclides. Quantities in JENDL-3.2 were extensively re-evaluated or replaced by more reliable values. The heavy nuclide data in JENDL-3.3 were validated with several benchmark tests, and it was reported that the current release gave a good prediction of criticalities.
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.
; Murata, Eiichi*; Sawahata, Yoshikazu*; Saito, Akira*
JNC TN8430 2001-002, 43 Pages, 2001/02
JNC-TN8430-2001-002.pdf:1.98MB
Japan Nuclear Cycle Development Institute (JNC) is designing the Low level radioactive Waste Treatment Facility (LWTF) in the Tokai Reprocessing Plant (TRP). The low level liquid waste generated the TRP is separated salt (NaNO
, etc) and radionuclide in liquid treatment process of LWTF. The process can get higher volume reduction than previous bituminization. Based on the engineering tests equal to the liquid treatment process of LWTF, the validity of operational condition in LWTF is evaluated. As the results, it is confirmed that all operational condition in the processes which is Iodine immobilization, Pre-filter filtration, Pre-treatment, Coprecipitation and Ultrafiltration are available.
Fukahori, Tokio; Chiba, Satoshi; Shibata, Keiichi; Ikeda, Yujiro; Aruga, Takeo; Watanabe, Yukinobu*; Murata, Toru*; Yamano, Naoki*; Kawai, Masayoshi*
Reactor Dosimetry: Radiation Metrology and Assessment (ASTM STP 1398), p.591 - 598, 2001/00
no abstracts in English
Kawano, Toshihiko*; Matsunobu, Hiroyuki*; Murata, Toru*; Zukeran, Atsushi*; Nakajima, Yutaka*; Kawai, Masayoshi*; Iwamoto, Osamu; Shibata, Keiichi; Nakagawa, Tsuneo; Osawa, Takaaki*; et al.
Journal of Nuclear Science and Technology, 37(4), p.327 - 334, 2000/04
no abstracts in English
U,U,
U,
Pu,
Pu,and 
PuKawano, Toshihiko*; Matsunobu, Hiroyuki*; Murata, Toru*; Zukeran, Atsushi*; Nakajima, Yutaka*; Kawai, Masayoshi*; Iwamoto, Osamu; Shibata, Keiichi; Nakagawa, Tsuneo; Osawa, Takaaki*; et al.
JAERI-Research 2000-004, p.76 - 0, 2000/02
JAERI-Research-2000-004.pdf:2.39MB
no abstracts in English
B, 
B, 
Mn, Pu and Pu neutron nuclear data in JENDL-3.2Shibata, Keiichi; *; Murata, Toru*
JAERI-Research 98-045, 48 Pages, 1998/08
JAERI-Research-98-045.pdf:1.64MB
no abstracts in English
O,
Na,Fe,U,U and Pu neutron nuclear data in JENDL-3.2Shibata, Keiichi; *; Kawano, Toshihiko*; S.Oh*; Matsunobu, Hiroyuki*; Murata, Toru*
JAERI-Research 97-074, 68 Pages, 1997/10
JAERI-Research-97-074.pdf:1.78MB
no abstracts in English
Shibata, Keiichi; Chiba, Satoshi; Fukahori, Tokio; Hasegawa, Akira; Iwamoto, Osamu; *; *; Kawano, Toshihiko*; Matsunobu, Hiroyuki*; Murata, Toru*; et al.
Proc. of Int. Conf. on Nucl. Data for Science and Technol., p.904 - 906, 1997/00
no abstracts in English
Shibata, Keiichi; Nakagawa, Tsuneo; Chiba, Satoshi; Iwamoto, Nobuyuki; Furutaka, Kazuyoshi; Murata, Toru*; Zukeran, Atsushi*; Matsunobu, Hiroyuki*
no journal, ,
We are developing the 4th Version of Japanese Evaluated Nuclear Data Library (JENDL-4) as the middle-term project. The resolved resonance paramters of FP nuclides have been evaluated in cooperation with the Japanese Nuclear Data Committee. The evaluation covers about 200 nuclides from Zn (Z=30) to Er (Z=68). Evaluation procedures and results of the resolved resonance parameters will be reported in this talk.
Suzuki, Yuji*; Kametaka, Masao*; Murata, Seiichi*; Aoki, Kazuhiro; Tanaka, Yoshihiro; Seshimo, Kazuyoshi; Sakai, Toru*
no journal, ,
no abstracts in English
Suzuki, Yuji*; Kametaka, Masao*; Aoki, Kazuhiro; Seshimo, Kazuyoshi; Murata, Seiichi*
no journal, ,
no abstracts in English
