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JAEA Reports

Studies on release behavior of radioactive noble gases from fuel solution to gas phase under simulated nuclear criticality accident (Contract research)

Abe, Hitoshi; Tashiro, Shinsuke; Koike, Tadao; Okagawa, Seigo; Uchiyama, Gunzo

JAERI-Research 2001-027, 20 Pages, 2001/03

JAERI-Research-2001-027.pdf:1.0MB

no abstracts in English

Journal Articles

Effects of helium production and irradiation damage on tritium release behavior of neutron-irradiated beryllium pebbles

Ishitsuka, Etsuo; Kawamura, Hiroshi; Terai, Takayuki*; Tanaka, Satoru*

Journal of Nuclear Materials, 283-287(Part.2), p.1401 - 1404, 2000/12

 Times Cited Count:7 Percentile:46.85(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Isotope exchange capacity of solid breeder materials

Baba, Atsushi*; Nishikawa, Masabumi*; Kawamura, Yoshinori; Okuno, Kenji

Journal of Nuclear Materials, 248, p.106 - 110, 1997/09

 Times Cited Count:4 Percentile:37.09(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Release behavior of decay helium from zirconium-cobalt tritide

Hayashi, Takumi; Amano, Junzo; Okuno, Kenji; Naruse, Yuji

Fusion Technology, 21, p.845 - 849, 1992/03

no abstracts in English

Journal Articles

Design and installation of "In-pile tritium-release experimental apparatus"; In-situ situdy of tritium release from uranium dioxides

Aratono, Yasuyuki; Nakashima, Mikio; Saeki, Masakatsu; Tachikawa, Enzo

Nihon Genshiryoku Gakkai-Shi, 27(2), p.139 - 144, 1985/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Synthesis of CeO$$_{2}$$ based simulated fuel containing CsI to evaluate the release behavior of Cs and I

Takamatsu, Yuki*; Kurosaki, Ken*; Ishii, Hiroto*; Osaka, Masahiko; Nakajima, Kunihisa; Miwa, Shuhei; Di Lemma, F. G.; Oishi, Yuji*; Muta, Hiroaki*; Yamanaka, Shinsuke*

no journal, , 

We performed spark plasma sintering tests of the cerium dioxide (CeO$$_{2}$$)-based simulated fuel containing cesium iodide (CsI) for the establishment of synthesis technology of simulated fuel containing volatile fission product (FP) such as cesium (Cs) and iodine (I) which is required for the data acquisition on the FP release behavior. We could successfully fabricate the simulated fuel containing CsI, which had homogeneous distribution of CsI compound, by the spark plasma sintering at lower temperature and in shorter time.

Oral presentation

Synthesis and characterization of CeO$$_{2}$$-based simulated fuel containing CsI

Takamatsu, Yuki*; Kurosaki, Ken*; Ishii, Hiroto*; Oishi, Yuji*; Muta, Hiroaki*; Yamanaka, Shinsuke*; Nakajima, Kunihisa; Suzuki, Eriko; Miwa, Shuhei; Osaka, Masahiko

no journal, , 

We performed spark plasma sintering tests of the cerium dioxide (CeO$$_{2}$$)-based simulated fuel containing cesium iodide (CsI), in order to establish a synthesis technology of simulated fuel including volatile fission product (FP) such as cesium (Cs) and iodine (I) for a study on the FP release behavior. We could successfully fabricated the simulated fuel containing CsI by the spark plasma sintering at lower temperature and in shorter time. It has homogeneous distribution of CsI compound in the sintered pellet.

Oral presentation

Effect of the atmosphere condition on the hydrogen desorption behavior of Ta

Kaneda, Tomohiro*; Yokoyama, Kenichi*; Ishijima, Yasuhiro; Ueno, Fumiyoshi; Abe, Hitoshi

no journal, , 

In spent nuclear fuel reprocessing plant, Zr/Ta dissimilar metal joint is used for connect between different devices. And it is known that Ta have susceptibility of hydrogen embrittlement. The other hand, it is not clear that relationship between hydrogen desorption behavior and hydrogen existing state in Ta. This study aims to elucidate the effect of environment for hydrogen desorption behavior on Ta. Thermal desorption spectroscopy (TDS) were carried out after hydrogen charging in 0.9% NaCl solution. Hydrogen desorption started at 873K, 673K and 573K in air, Ar and ultra-high vacuum environment respectively. After TDS in air environment, specimen was covered with Ta$$_{2}$$O$$_{5}$$ film. After removal of the film, hydrogen desorption was observed from 773K in argon environment. These results suggest that the generation of the Ta$$_{2}$$O$$_{5}$$ film suppresses the hydrogen desorption from Ta. And it shows that when considering the relationship between the existence state of hydrogen in Ta with thermal aging, it is necessary to consider the influence of the Ta$$_{2}$$O$$_{5}$$ film.

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