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Miwa, Kazuji; Terasaka, Yuta; Ochi, Kotaro; Futemma, Akira; Sasaki, Miyuki; Hirouchi, Jun
Nihon Genshiryoku Gakkai-Shi ATOMO
, 61(9), p.687 - 691, 2019/09
This report summarizes the contents of the session of the Health Physics and Environment Science Division, which was held in Atomic Energy Society of Japan 2019 Spring Meeting. In this session, six students and young researchers who engaged in the field of nuclear energy and radiation gave a lecture about health physics and environmental science research through their expertise. After the all presentations end, we took discussion time about the issues and future development in this field with all attendees. In this report, we summarized each lecture outline and discussion contents.
Hoshino, Yuzuru; Sakamoto, Yoshiaki; Muroi, Masayuki*; Mukai, Satoru*
JAEA-Technology 2015-015, 96 Pages, 2015/07
JAEA-Technology-2015-015.pdf:20.34MB
In order to dispose of the radioactive waste which generates from post-irradiation examination (PIE) facilities, the common evaluation method of radioactivity in wastes from PIE should be established by the actual data such as radioactivity values and the theoretical calculation. In this study, the radioactivity concentrations of 17 nuclides (H-3, C-14, Co-60, Ni-63, Sr-90, Tc-99, Cs-137, Eu-154, U-234, U-235, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Am-241, Cm-244) in combustible wastes stored in NUCLEAR DEVELOPMENT CORPORATION were measured from 3 samples and the radioactivity was calculated by ORIGEN-2 based on initial contents and operation record of the spent fuel. From the comparison of the obtained data by the radiological measurement with the calculated values, the subject to be solved for establishment of the radioactivity evaluation method for PIE was extracted.
Asai, Shiho; Sakai, Akihiro; Yoshimori, Michiro; Kihara, Shinji
JAERI-Tech 2003-071, 46 Pages, 2003/08
JAERI-Tech-2003-071.pdf:4.31MB
As part of survey concerning radioactive inventory of radwastes arising from research institutes, an analytical scheme has been studied for verifying their nuclide composition based on calculation analysis and record, in consideration of the its characteristics. In this study, radwastes are used as samples, which arise from research and testing reactors and post-irradiation examination facilities (PIE facilities). Though separation procedures are simplified and rationalized, quantifiable values could be obtained with relative errors under 10% for almost all the samples containing nuclides like 
Ni and 
U which concentrations are low, and recoveries were high on the whole. These show that the analytical scheme is useful for chemical separation of radwastes arising from research and testing reactors and PIE facilities.
Nomura, Yasushi; Mochizuki, Hiroki*
JAERI-Tech 2002-068, 131 Pages, 2002/11
JAERI-Tech-2002-068.pdf:5.59MB
no abstracts in English
Mochizuki, Hiroki*; Suyama, Kenya; Nomura, Yasushi; Okuno, Hiroshi
JAERI-Data/Code 2001-020, 394 Pages, 2001/08
JAERI-Data-Code-2001-020.pdf:17.99MB
no abstracts in English
Nakahara, Yoshinori; Suyama, Kenya; Suzaki, Takenori
JAERI-Tech 2000-071, 381 Pages, 2000/10
JAERI-Tech-2000-071.pdf:17.6MB
no abstracts in English
Sakai, Akihiro; Yoshimori, Michiro; Abe, Masayoshi
JAERI-Tech 2000-012, p.107 - 0, 2000/03
JAERI-Tech-2000-012.pdf:6.47MB
no abstracts in English
Matsunaga, Takeshi; Ueno, Takashi; Amano, Hikaru; Y.Tkatchenko*; A.Kovalyov*; Watanabe, Miki*; Onuma, Yoshikazu*
Journal of Contaminant Hydrology, 35, p.101 - 113, 1998/00
Times Cited Count：44 Percentile：74.63(Environmental Sciences)no abstracts in English
Suyama, Kenya
JAERI-Data/Code 97-045, 26 Pages, 1997/11
JAERI-Data-Code-97-045.pdf:2.31MB
no abstracts in English
Naito, Yoshitaka; ; Kurosawa, Masayoshi; Suzaki, Takenori
Nuclear Technology, 110, p.40 - 52, 1995/04
Times Cited Count：3 Percentile：36.75(Nuclear Science & Technology)no abstracts in English
Sugiyama, Daisuke*; Koma, Yoshikazu; Takahatake, Yoko; Aoki, Yoshio*; Nakabayashi, Ryo*; Fujita, Tomonari*
no journal, ,
The introduction of a stochastic approach to the calibration of the radionuclide transport parameters, which processes the frequency distribution of the analytical measured data accumulated progressively on the wastes and contaminated water, into the modelling estimation method of the radioactive waste inventory generated at the Fukushima Daiichi Nuclear Power Station is investigated. It is expected that the accuracy of the modelling estimation of radionuclide composition in wastes will be improved by describing the radionuclide transport parameters as a lognormal distribution.
Miyabe, Masabumi; Oba, Masaki; Akaoka, Katsuaki; Wakaida, Ikuo
no journal, ,
In the decommissioning of the Fukushima Daiichi Nuclear Power Plant, remote elemental and isotopic analysis of highly radioactive substances containing actinide elements, fission products, and reactor materials is of great importance. The composition information is required for various purposes such as verification of safeguards, prevention of recriticality accident, and planning of waste treatment procedure. However, in radiochemical analysis, owing to its limited energy resolution it is very difficult to identify individual nuclides of U and Pu, and because there are various isobars produced through radiative decay chain, isotopic analysis with mass spectrometry is also difficult. Thus we are developing a remote isotopic analytical technique combining atomic absorption spectroscopy and laser ablation technique. Various experimental conditions were optimized to realize highly sensitive and isotope selective analysis. Also, in order to reduce the Doppler effect and the Stark effect, we investigated the expansion behavior of the ablation plume to clarify underlying physics. Moreover, the analytical performance was evaluated using a mixture oxide samples of uranium and plutonium, and good performances were obtained. Furthermore, in order to apply this method to the analysis of nano-particles generated with laser cutting etc., we studied the method of decomposing nano-particles into atoms. We would like to report on the current status and future prospects of the development of this new analytical technique.
Kagayama, Yuichi*; Sagara, Hiroshi*; Han, C. Y.*; Kimura, Yoshiki
no journal, ,
no abstracts in English
Watanabe, Tomoaki; Kikuchi, Takeo; Tonoike, Kotaro; Suyama, Kenya
no journal, ,
In order to obtain new post irradiation examination data for validation of burnup calculation codes, isotopic compositions of 9 samples obtained from a 17
17 high-burnup lead use assembly (53 GWd/t), which was irradiated in Ohi Nuclear Power Station Unit 4, were measured. The isotopic compositions were also evaluated by burnup calculations with SWAT4.0 code and compared with the measurements.
