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Journal Articles

Effect of carbonate concentration on the dissolution rates of UO$$_{2}$$ and spent fuel; A Review

Kitamura, Akira; Akahori, Kuniaki*

Advances in Materials Science for Environmental and Energy Technologies, 6, p.133 - 144, 2017/10

The Japanese geological disposal program has started researching disposal of spent nuclear fuel (SF) in deep geological strata as an alternative management option other reprocessing followed by vitrification and geological disposal of high-level radioactive waste. One of the key parameters for SF disposal other than the disposal of high-level radioactive waste is the fuel dissolution rate. Carbonate concentration in the simulated water composition with contact to SF after canister breaching in the Japanese SF disposal system is around 10$$^{-2}$$ mol dm$$^{-3}$$, which is one order of magnitude larger than those in some countries in Europe. The SF dissolution rate will be depend on carbonate concentration due to promoting oxidative dissolution of SF by formation of carbonate complexes of uranium(VI). For evaluation of reliable SF dissolution rate in the Japanese SF disposal system as an alternative management option, effect of carbonate concentration on dissolution rate of UO$$_{2}$$ and spent fuel has been reviewed.

Oral presentation

Effects of $$alpha$$-radiation on a disposal of spent nuclear fuel

Kitamura, Akira

no journal, , 

The Japanese geological disposal program has started researching disposal of spent nuclear fuel (SF) in deep geological strata (hereafter "direct disposal of SF") as an alternative management option other reprocessing followed by vitrification and geological disposal of high-level radioactive waste. In the case of direct disposal of SF, specific examples of the possible effects of radiation include: generation of oxidizing chemical species in conjunction with decomposition of groundwater and accompanying oxidation of reducing groundwater; and increase in the dissolution rate of SF and the solubility of radionuclides. Focusing especially on the effects of $$alpha$$-radiation in safety assessment, this study has reviewed research into the effects of $$alpha$$-radiation on the spent nuclear fuel, canisters and environment outside the canisters, and safety assessments in countries other than Japan that are planning direct disposal of SF. It was found that the effects of $$alpha$$-radiation on SF disposal are not significant due to suppression of water radiolysis by hydrogen gas generated from canister corrosion according to the latest research.

Oral presentation

Two step pressurization in pulsed electric current sintering of MoO$$_{3}$$ for production of radioactive isotopes

Suematsu, Hisayuki*; Seki, Misaki*; Sato, Soma*; Nanko, Makoto*; Tsuchiya, Kunihiko; Nishikata, Kaori; Suzuki, Tsuneo*; Nakayama, Tadachika*; Niihara, Koichi*

no journal, , 

no abstracts in English

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