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Oral presentation

Influence of $$^{60}$$Co $$gamma$$-ray on characteristics of phosphate cements synthesized during dehydration

Irisawa, Keita; Kudo, Isamu*; Taniguchi, Takumi; Namiki, Masahiro*; Osugi, Takeshi; Nakazawa, Osamu

no journal, , 

no abstracts in English

Oral presentation

Investigation of hydrogen gas generation by $$gamma$$-ray irradiation for cement-solidified products of used adsorbents for water decontamination

Sato, Junya; Kikuchi, Hiroshi*; Kato, Jun; Sakakibara, Tetsuro; Matsushima, Ryotatsu; Sato, Fuminori; Kojima, Junji; Nakazawa, Osamu

no journal, , 

no abstracts in English

Oral presentation

Application of ferrite process to radioactive waste; Study of ferrite product stability by Micro-PIXE analysis

Abe, Tomohisa; Shimazaki, Takejiro; Osone, Osamu*; Osugi, Takeshi; Nakazawa, Osamu; Yuri, Yosuke*; Yamada, Naoto*; Sato, Takahiro*

no journal, , 

no abstracts in English

Oral presentation

Development of radiation resistant monitoring system for LWR

Takeuchi, Tomoaki; Otsuka, Noriaki; Tsuchiya, Kunihiko; Tanaka, Shigeo*; Ozawa, Osamu*; Komanome, Hirohisa*

no journal, , 

no abstracts in English

Oral presentation

$$gamma$$-ray resistant assessment of MA adsorbent for the next generation vitrification

Miyazaki, Yasunori; Sano, Yuichi; Kofuji, Hirohide; Watanabe, So; Koka, Masashi*; Sato, Takahiro*

no journal, , 

no abstracts in English

Oral presentation

Fabrication of novel neutron optical devices using proton microbeam, 2

Sakai, Takuro; Iikura, Hiroshi; Yamada, Naoto*; Sato, Takahiro*; Ishii, Yasuyuki*; Uchida, Masaya*

no journal, , 

no abstracts in English

Oral presentation

Radiolytic hydrogen absorption behavior of dissimilar metal joint under $$gamma$$-ray irradiation in nitric acid solution

Ishijima, Yasuhiro; Ueno, Fumiyoshi; Abe, Hitoshi

no journal, , 

Explosion-bonded metal joint has been used at the spent nuclear fuel reprocessing plant in Japan. The metal joint is made of zirconium, tantalum and R-SUS304ULC. And the radiolytic hydrogen is known to be generated in the spent nuclear fuel solution. Also, tantalum is known to be highly susceptible to hydrogen embrittlement. Therefore, evaluating the radiolytic hydrogen absorption behavior of metal joint in nitric acid solution (HNO$$_{3}$$) is essential. In this study, immersion tests were conducted on tantalum in nitric acid solutions under $$gamma$$-ray irradiation to evaluate its radiolytic hydrogen adsorption behavior. Results showed that the radiolytic hydrogen absorbed in zirconium near the Zr/Ta interface. But, hydrogen embrittlement was not observed in tensile test under $$gamma$$-ray irradiation. The reason was considered that the radiolytic hydrogen was trapped at the surface of the zirconium as hydride.

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