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JAEA Reports

Development of production methods of the Sr-90/Y-90 source for hydrogen production experiments

Motoki, Riyozo; Aoki, Hiromichi; Uchida, Shoji; Nagaishi, Ryuji; Yamada, Reiji

JAEA-Technology 2008-014, 23 Pages, 2008/03

JAEA-Technology-2008-014.pdf:9.05MB

The study of producing hydrogen with a Sr-90/Y-90 source is planned to utilze the radioactive waste effectively. Therefore we developed two methods of caking Sr-90 and a catalyst for the production of hydrogen effectively. One is a method of caking $$^{90}$$SrTiO$$_{3}$$ and TiO$$_{2}$$ in a silica gel. And another is a method of caking $$^{90}$$SrSO$$_{4}$$ and TiO$$_{2}$$ in a silica gel. These solid matters are porous materials, which has a radiation resistant and chemical resistant. In addition, Y-90 which is a daughter nuclide of Sr-90 can be also used for hydrogen production.

JAEA Reports

Analytical work at NUCEF in FY 2006

Sakazume, Yoshinori; Aoki, Hiromichi; Haga, Takahisa; Fukaya, Hiroyuki; Sonoda, Takashi; Shimizu, Kaori; Niitsuma, Yasushi*; Ito, Mitsuo; Inoue, Takeshi

JAEA-Technology 2007-069, 44 Pages, 2008/02

JAEA-Technology-2007-069.pdf:4.55MB

Analysis of the uranyl nitrate solution fuel is carried out at the analytical laboratory of NUCEF (Nuclear Fuel Cycle Engineering Research Facility), which provides essential data for operation of STACY (Static Experiment Critical Facility), TRACY (Transient Experiment Critical Facility) and the fuel treatment system. Analyzed in FY 2006 were uranyl nitrate solution fuel samples taken before and after experiments of STACY and TRACY, samples for the preparation of uranyl nitrate solution fuel, and samples for nuclear material accountancy purpose. The total number of the samples analyzed in FY 2006 was 254. This report summarizes work related to the analysis and management of the analytical laboratory in the FY 2006.

JAEA Reports

Analytical work at NUCEF in FY 2005

Fukaya, Hiroyuki; Aoki, Hiromichi; Haga, Takahisa; Nishizawa, Hidetoshi; Sonoda, Takashi; Sakazume, Yoshinori; Shimizu, Kaori; Niitsuma, Yasushi*; Shirahashi, Koichi; Inoue, Takeshi

JAEA-Technology 2007-005, 27 Pages, 2007/03

JAEA-Technology-2007-005.pdf:1.97MB

Analysis of the uranyl nitrate solution fuel is carried out at the analytical laboratory of NUCEF (Nuclear Fuel Cycle Engineering Research Facility), which provides essential data for operation of STACY (Static Experiment Critical Facility), TRACY (Transient Experiment Critical Facility) and the fuel treatment system. Analyzed in FY 2005 were uranyl nitrate solution fuel samples taken before and after experiments of STACY and TRACY, samples for the preparation of uranyl nitrate solution fuel, and samples for nuclear material accountancy purpose. Also analyzed were the samples from raffinate treatment and its preliminary tests. The raffinate was generated, since FY 2000, during preliminary experiments on U/Pu extraction-pulification to fix the operation condition to prepare plutonium solution fuel to be used for criticality experiments at STACY. This report summarizes work related to the analysis and management of the analytical laboratory in the FY 2005.

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