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Journal Articles

Safety demonstration project on disposing of contaminated soil in Tokai-mura

Murata, Chinatsu; Kitahara, Masaru; Tanaka, Kiwamu; Amazawa, Hiroya; Takebe, Shinichi; Yamada, Osamu*; Kameo, Yutaka

Dekomisshoningu Giho, (62), p.20 - 31, 2020/09

On the basis of Act on Special Measures, municipalities stripped surface soil off the playground of park to decontaminate the soil which had been contaminated with radionuclides released from Fukushima Daiichi Nuclear Power Plant. To minimize the exposure dose of the residents, it was essential to decide safe disposal of the contaminated soil which has been stored at temporary storage areas. Therefore, the ministry of the Environment and Tokai-mura office required Japan Atomic Energy Agency (JAEA) to perform demonstration project of burying the contaminated soil generated by decontamination of public facilities in order to provide decision on the enforcement ordinance and guidelines of burying it. In this project, we acquired data of air dose rate and the personal exposure dose during transporting, burying, and storing the contaminated soil. In addition, we measured radioactivity concentration of dust collected from surroundings of the landfill and seepage water through contaminated soil.

Journal Articles

Study on decontamination of steel surface contaminated with uranium hexafluoride by acidic electrolytic water

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$$^{2}$$), 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.

Journal Articles

QA/QC activities and estimation of uncertainty for ultra-trace analysis of uranium and plutonium in safeguards environmental samples

Usuda, Shigekazu*; Magara, Masaaki; Esaka, Fumitaka; Yasuda, Kenichiro; Kokubu, Yoko; Lee, C. G.; Miyamoto, Yutaka; Suzuki, Daisuke; Inagawa, Jun; Sakurai, Satoshi; et al.

Journal of Nuclear and Radiochemical Sciences, 11(2), p.A5 - A9, 2011/01

In the analysis of IAEA safeguards environmental samples, isotope ratios of ultra-trace amounts of uranium and plutonium in samples taken from nuclear facilities are determined to detect undeclared nuclear materials and activities. In order to keep and enhance the reliability of the measurement results, validation of analytical methods and estimation of measurement uncertainty in such ultra-trace analysis should be properly done in accordance with worldwide standards. In this paper, the current activities on achievement of QA/QC (quality assurance and quality control) and estimation of measurement uncertainty in the ultra-trace analysis at a clean chemistry laboratory (CLEAR) of JAEA are reported.

JAEA Reports

Extraction and separation of uranium from simulated uranium-containing liquid wastes of Ningyo-toge environmental engineering center

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.

Journal Articles

Methods to extract information on the atomic and molecular states from scientific abstracts

Sasaki, Akira; Murata, Masaki*; Kanamaru, Toshiyuki*; Shirado, Tamotsu*; Isahara, Hitoshi*; Ueshima, Yutaka; Yamagiwa, Mitsuru

Purazuma, Kaku Yugo Gakkai-Shi, 81(9), p.717 - 722, 2005/09

no abstracts in English

JAEA Reports

Evaluations of heavy nuclide data for JENDL-3.3

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.

Journal Articles

Japanese evaluated nuclear data library version 3 revision-3; JENDL-3.3

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:649 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 $$^{235}$$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.

Journal Articles

Shear Properties and Permeability of the Joint of Bentonite Buffer for Geological Disposal of High-Level Radioactive Waste

Imamura, Masahiro*; Chijimatsu, Masakazu*; Sugita, Yutaka; Kikuchi, Hirohito*; Murata, Sumihiko*; Amemiya, Kiyoshi*; Saito, Toshiaki*

Doboku Gakkai Rombunshu, (673), p.61 - 70, 2001/00

None

Journal Articles

Simultaneous evaluation of fission cross sections of uranium and plutonium isotopes for JENDL-3.3

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

JAEA Reports

Evaluation of fission cross sections and covariances for $$^{233}$$U,$$^{235}$$U,$$^{238}$$U,$$^{239}$$Pu,$$^{240}$$Pu,and $$^{241}$$Pu

Kawano, 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

Journal Articles

Neutron and $$gamma$$ ray radiography using a multi-color converter

Iwata, Hideki*; Mochiki, Koichi*; Murata, Yutaka*; Nitto, Koichi*; Tamura, Toshiyuki*; Kobayashi, Hisao*; Matsubayashi, Masahito

Dai-3-Kai Hoshasen Ni Yoru Hihakai Hyoka Shimpojiumu Koen Rombunshu, p.142 - 147, 1999/11

no abstracts in English

Journal Articles

JENDL-3.2 covariance file for fast reactors

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

Journal Articles

Application of neutron radiography to visualization of cryogenic fluid boiling two-phase flows

Takenaka, Nobuyuki*; Asano, Hitoshi*; Fujii, Terushige*; Ushiro, Toshihiko*; Iwatani, Junji*; Murata, Yutaka*; Mochiki, Koichi*; Taguchi, Akira*; Matsubayashi, Masahito; Tsuruno, Akira

Nuclear Instruments and Methods in Physics Research A, 377(1), p.174 - 176, 1996/07

 Times Cited Count:1 Percentile:23.68(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Compressed air energy storage system two-phase flow experiment

Kumamaru, Hiroshige; ; Murata, Hideo; Kukita, Yutaka; Akiyama, Mamoru*; *; *; *; *; *; et al.

Proc. of ASME$$cdot$$JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 1(PART B), p.669 - 674, 1996/00

no abstracts in English

Journal Articles

Measurement of local void fraction distribution in rod bundle under high-pressure high-temperature boil-off conditions by using optical void probe

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

Journal Articles

Void-fraction distribution under high-pressure boil-off conditions in rod bundle geometry

Kumamaru, Hiroshige; ; Murata, Hideo; Kukita, Yutaka

Nucl. Eng. Des., 150, p.95 - 105, 1994/00

 Times Cited Count:29 Percentile:90.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Startup Experiment of a PIUS-type reactor from isothermal fluid condition by feedback control of primary pump

*; *; 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

JAEA Reports

Core void fraction distribution under high-temperature high-pressure boil-off conditions; Experimental study with two-phase flow test facility(TPTF)

; Kumamaru, Hiroshige; Murata, Hideo; Anoda, Yoshinari; Kukita, Yutaka

JAERI-M 93-200, 56 Pages, 1993/10

JAERI-M-93-200.pdf:1.85MB

no abstracts in English

Journal Articles

Feedback control of primary pump using midplane temperature of lower density lock for a PIUS-type reactor

*; 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

32 (Records 1-20 displayed on this page)