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Yamagishi, Shigetada*; Hayashida, Takeshi*; Misawa, Ryusuke*; Kimura, Kenta*; Hagihara, Masato; Murata, Tomoki*; Hirose, Sakyo*; Kimura, Tsuyoshi*
Chemistry of Materials, 35(2), p.747 - 754, 2023/01
Times Cited Count：5 Percentile：91.39(Chemistry, Physical)
)Komatsu, Kazuki*; Iwasaki, Tsugumi*; Murata, Kosuke*; Yamashiro, Hideaki*; Goh, V. S. T.*; Nakayama, Ryo*; Fujishima, Yohei*; Ono, Takumi*; Kino, Yasushi*; Shimizu, Yoshinaka*; et al.
Reproduction in Domestic Animals, 56(3), p.484 - 497, 2021/03
Times Cited Count：9 Percentile：87.04(Agriculture, Dairy & Animal Science)We have established an archive system of livestock and wild animals from the surrounding ex-evacuation zone. Wildlife within the alert zone have been exposed to low-dose-rate (LDR) radiation for a long and continuous time. In this study, we analysed the morphological characteristics of the testes and in vitro fertilization (IVF) capacity of cryopreserved sperm of raccoons from the ex-evacuation zone of the FDNPP accident. This study revealed that the chronic and LDR radiation exposure associated with the FDNPP accident had no adverse effect on the reproductive characteristics and functions of male raccoons.
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.
Ohashi, Yusuke; Tsunashima, Yasumichi; Murata, Masato
Proceedings of 2nd International Conference on Sustainable Development through Nuclear Research and Education (Nuclear 2009) (CD-ROM), p.161 - 168, 2009/05
Solid and liquid radioactive waste derived from various research such as technology development for uranium refining and conversion stored currently totals 1500tons. NaF waste, used as an absorbent of UF
contains about 20-30wt% uranium. CaF
waste, which is generated from the disposal of waste water including fluoride, contains up to 20wt% uranium. Most of these are classified as intermediate disposal waste. Hence it is necessary to recover uranium to dispose waste as a shallow ground disposal waste. Dissolution experiments were carried out by charging CaF waste and NaF waste into 1N HCl. The dissolution rates of CaF waste and NaF waste were 99.8% and 100% respectively. The recovery rates of uranium from CaF solution and NaF solution were 98.2% and 99.7% respectively. It was confirmed that we could dispose these waste reasonably.
Mitamura, Hisayoshi; Naganawa, Hirochika; Nagano, Tetsushi; Yanase, Nobuyuki; Hanzawa, Yukiko; Shimojo, Kojiro; Matsubara, Tatsuo; Mita, Yutaka; Taki, Tomihiro; Murata, Masato
JAEA-Research 2008-113, 27 Pages, 2009/03
JAEA-Research-2008-113.pdf:31.84MB
An effective mass processing equipment using solvent extraction method, named "emulsion flow extractor," is the most promising apparatus for removal and recovery of uranium from liquid waste originated from decontamination of uranium-contaminated fluoride waste in the uranium conversion test facility and of used gas centrifuges in the uranium enrichment facility at Ningyo-toge environmental engineering center. Prior to application of the emulsion flow extractor for actual uranium-containing liquid waste, properties of some phosphorous extractants for extraction and separation of uranium and constituents from simulated liquid wastes were examined through batch tests. These preliminary tests revealed that D2EHPA would be a promising candidate for extractant used for treatment of the actual uranium-containing liquid wastes, and that the extractants with a surfactant like AOT would not be useful.
Takamiya, Kazuhiro; Murata, Masato
JNC TY6440 2004-001, 37 Pages, 2005/03
JNC-TY6440-2004-001.pdf:0.62MB
None
Murata, Masatoshi*; Miyahara, Tomoya*; Odagawa, Shinya*
JNC TJ7400 2005-048, 111 Pages, 2004/03
JNC-TJ7400-2005-048.PDF:12.01MB
In this study, some area precipitaions that were calculated Representation value method, Average rainfall method and Weighted average method was compared with runoff of these catchments. Calculation area method precipitaion was estimated by the correlation coefficient.
Miyahara, Tomoya*; Odagawa, Shinya*; Murata, Masatoshi*
JNC TJ5400 2004-001, 93 Pages, 2004/01
JNC-TJ5400-2004-001.pdf:12.38MB
The Horonobe Underground Research Center carried out surface hydrological investigation as a part of Horonobe Underground Research Laboratory project. This report describes the examination, was additional selection of everpotranspiration and precipitation measurement points in surface hydrological investigation. In this study, characteristic analysis of catchment carried out Shimizu River catchment and divided into three catchments of Penke-Ebekorobetu River catchment. Consequently, in surrounding catchment of the Horonobe Underground Research Laboratory site, it became clear that topography is low relief and highest forest type is broadleaf tree stands. The result which examined the applicability of the Everpotranspiration calculation method, applicability of profile method and Bowen's ratio thermal balance method in broadleaf tree forest, and applicability of Penman method in pastureland were high. Moreover, three additional everpotranspiration measurement sites and three additional precipitation measurement sites is selected using these results, in surrounding catchment of the Horonobe Underground Research Laboratory site.
Murata, Masatoshi*; Kato, Yoshiro*; Kobayashi, Koichi*
PNC TJ7361 92-001, 165 Pages, 1992/02
PNC-TJ7361-92-001.pdf:8.22MBPNC-TJ7361-92-001-attribute-list-A.pdf:25.4MBPNC-TJ7361-92-001-attribute-list-A-G.pdf:86.0MB
no abstracts in English
Murata, Masatoshi*; Yasuno, Masamitsu*; Wakamatsu, Hisanori; *;
JNC TJ7440 2000-029, 158 Pages, 1991/07
JNC-TJ7440-2000-029.pdf:7.15MB
no abstracts in English
*; Shimo, Michito*; Aoki, Kenji*; Horita, M.*; Murata, Masatoshi*
PNC TJ1449 91-015, 128 Pages, 1991/04
None
Murata, Masatoshi*
PNC TJ7361 90-006, 137 Pages, 1991/01
PNC-TJ7361-90-006.pdf:3.91MBPNC-TJ7361-90-006-attribute-list-A.pdf:15.09MBPNC-TJ7361-90-006-attribute-list-A-G.pdf:41.89MB
no abstracts in English
Murata, Masatoshi*; Yasuno, Masamitsu*;
JNC TJ7440 2001-008, 201 Pages, 1990/03
JNC-TJ7440-2001-008.pdf:6.65MB
no abstracts in English
Aoki, Kenji*; Sudo, Ken*; Ishii, Takashi*; Shimo, Michito*; Ochiishi, Masanobu*; Murata, Masatoshi*
JNC TJ7400 2005-063, 348 Pages, 1989/06
JNC-TJ7400-2005-063.pdf:19.24MB
None
Murata, Masatoshi*; Yasuno, Masamitsu*
JNC TJ7440 2001-010, 131 Pages, 1989/03
JNC-TJ7440-2001-010.pdf:6.24MB
no abstracts in English
Murata, Masatoshi*; Yasuno, Masamitsu*; *; *
JNC TJ7440 2001-007, 146 Pages, 1988/07
JNC-TJ7440-2001-007.pdf:14.86MB
no abstracts in English
Ohashi, Yusuke; Nakatsuka, Yoshiaki; Kawatsuma, Shinji; Hata, Haruhi; Tsunashima, Yasumichi; Murata, Masato; Tokizawa, Takayuki; Sugitsue, Noritake
no journal, ,
Sludge waste derived from research and discussion for uranium refining and conversion exclude much uranium. We must recover uranium from them from the point of view of use of resource and we dispose of residue generated by the process. We recovered uranium from real waste by water or hydrochloric acid. The dissolution rates of uranium from sludge from neutralization and NaF, filter medium, alumina, MgF wastes were more than 99% by 2 hour 1N HCl treatment. The dissolution rate of uranium from bed material waste was more than 99% by 24h 1N HCl treatment and addition of hydrogen peroxide. The dissolution rates of NaF, filter medium waste by water treatment were 99% and 88%. From the results, we confirmed dissolution characteristics of real waste as basic data to study recovery process of uranium.
Tsunashima, Yasumichi; Nakatsuka, Yoshiaki; Kawatsuma, Shinji; Ohashi, Yusuke; Murata, Masato; Tokizawa, Takayuki; Sugitsue, Noritake; Hata, Haruhi
no journal, ,
The operation waste generated from the uranium handling facilities of the uranium conversion and uranium enrichment, etc. is called a sludge. They are assumed to be execution of the uranium collection if necessary, cement solidification, and disposal. Therefore, the examination that confirmed the range where cement solidifies was executed. The cement kind, the water cement ratio, and the sludge mixture rate were assumed to be a parameter and the solidification test was executed. The range of solidification was confirmed by the bleeding water after 24 hours had passed. The uniaxial compression was measured with cement in the solidification condition. A possibility miscible from 40wt% to about 60wt% was able to be confirmed from these examination results in the absorbent (NaF pellet and active alumina), the bed materials (no active alumina), Neutralizing precipitation.
Murata, Masato; Katano, Yoshiaki; Usui, Hideo; Kubota, Shintaro
no journal, ,
As of October 2014, four Nuclear Power Plants, such as Tokai-1, Hamaoka Power Station Unit 1, Unit 2 and Fugen, have been carried out decommissioning, and JAEA's facilities, such as JRR-2, JRTF, RHL, PFFF, have been decommissioned, too. This presentation shows the decommissioning strategy and current status of decommissioning in Japan at ANUP2014.
