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Yamane, Yuichi; Amano, Yuki; Tashiro, Shinsuke; Abe, Hitoshi; Uchiyama, Gunzo; Yoshida, Kazuo; Ishikawa, Jun
Journal of Nuclear Science and Technology, 53(6), p.783 - 789, 2016/06
Times Cited Count:5 Percentile:43.41(Nuclear Science & Technology)The release behavior of radioactive materials from high active liquid waste (HALW) has been experimentally investigated under boiling accident conditions. In the experiments using HALW obtained through laboratory scale reprocessing, release ratio was measured for the FP nuclides such as Ru, Tc, Cs, Sr, Nd, Y, Mo, Rh and actinides such as Cm, Am. As a result, the release ratio was 0.20 for Ru and 1 for the FP and Ac nuclides. Ru was released into the gas phase in the form of both mist and gas. For its released amount, weak dependency was found to the initial concentration in the test solution. The release ratio decreased with the initial concentration. For other FP nuclides and actinides as non-volatile, released into the gas phase in the form of mist, the released amount increased with the initial concentration. The release ratio of Ru and NOx concentration increased with temperature of the test solutions. They were released almost at the same temperature between 200 and 300C. Size distribution of the mist and other particle was measured.
Enoeda, Mikio
JAERI-Conf 2004-012, 237 Pages, 2004/07
This report is the Proceedings of "the Eleventh International Workshop on Ceramic Breeder Blanket Interactions" which was held as a workshop on ceramic breeders Under the IEA Implementing Agreement on the Nuclear Technology of Fusion Reactors, and the Japan-US Fusion Collaboration Framework. In the workshop, information exchange was performed for designs of solid breeder blankets and test blankets in EU, Russia and Japan, recent results of irradiation tests, HICU, EXOTIC-8 and the irradiation tests by IVV-2M, modeling study on tritium release behavior of LiTiO and other breeders, fabrication technology developments and characterization of the LiTiO and LiSiO pebbles, research on measurements and modeling of thermo-mechanical behaviors of LiTiO and LiSiO pebbles, and interfacing issues, such as, fabrication technology for blanket box structure, neutronics experiments of blanket mockups by fusion neutron source and tritium recovery system.
Atarashi-Andoh, Mariko; Amano, Hikaru; Kakiuchi, Hideki; Ichimasa, Michiko*; Ichimasa, Yusuke*
Health Physics, 82(6), p.863 - 868, 2002/06
Times Cited Count:6 Percentile:39.54(Environmental Sciences)As a substitute of tritium, deuterium water (D2O) vapor release experiments were performed to estimate the difference of formation and subsequent retention of organically bound deuterium (OBD) in rice plants between daytime and nighttime exposure. Potted plants were exposed to deuterium water vapor in a greenhouse for 8 hours, under day and night conditions. Deuterium concentrations in free water and organic matter in rice leaves and ears were investigated until the harvest time. Data analysis was carried out using a model in which different generating processes of organic matter were considered. The calculated results agreed with the measured value.
Atarashi-Andoh, Mariko; Amano, Hikaru; Ichimasa, Michiko*; Ichimasa, Yusuke*
Fusion Science and Technology, 41(3), p.427 - 431, 2002/05
In processes of tritium transfer in the environment, conversion of HTO to OBT in plant by photosynthesis is important for both aspects of monitoring and dose estimation. Because once OBT is formed in plant, it stays in the plant for longer time than HTO, and OBT is more harmful than HTO for human body. Conversion rate of HTO in plant leaf to OBT in plant edible parts in the open air were obtained for some plants (komatsuna, radish and cherry tomato) during the chronic HT release experiment at Chalk River in 1994. At the experiment, HT gas was released to the atmosphere at the cultivated site for 12 days continuously [1]. HTO and OBT concentration in cultivated plants were measured during the experiment. For plant leaves conversion rate of HTO to OBT was about 0.2 (% h) but it varied with their growth stage. A chamber experiment in laboratory was also carried out for comparison.
Noguchi, Hiroshi; Fukutani, Satoshi*; Yokoyama, Sumi; Kinouchi, Nobuyuki
KURRI-KR-61, p.18 - 25, 2000/00
no abstracts in English
Noguchi, Hiroshi; Yokoyama, Sumi; Fukatani, S.*; Kinouchi, Nobuyuki; Murata, Mikio; Amano, Hikaru; Atarashi-Andoh, Mariko
JAERI-Data/Code 99-022, 125 Pages, 1999/03
no abstracts in English
Noguchi, Hiroshi
Purazuma, Kaku Yugo Gakkai-Shi, 73(12), p.1350 - 1351, 1997/12
no abstracts in English
Murata, Mikio; Noguchi, Hiroshi
Journal of Nuclear Science and Technology, 34(2), p.176 - 184, 1997/02
Times Cited Count:1 Percentile:14.48(Nuclear Science & Technology)no abstracts in English
J.Yan*; Maruyama, Yu; Sugimoto, Jun
JAERI-Tech 95-052, 27 Pages, 1995/12
no abstracts in English
Ichimasa, Yusuke*; Ichimasa, Michiko*; H.Jiang*; *; Noguchi, Hiroshi; Yokoyama, Sumi; Amano, Hikaru; Atarashi, Mariko
Fusion Technology, 28, p.877 - 882, 1995/10
no abstracts in English
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JAERI-M 85-208, 53 Pages, 1986/01
no abstracts in English
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JAERI-M 83-233, 60 Pages, 1984/01
no abstracts in English
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Nihon Genshiryoku Gakkai-Shi, 26(6), p.526 - 534, 1984/00
Times Cited Count:5 Percentile:51.32(Nuclear Science & Technology)no abstracts in English
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JAERI-M 82-156, 17 Pages, 1982/11
no abstracts in English