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Journal Articles

Review of ADS and P&T Programme in Japan

Oigawa, Hiroyuki

NEA/NSC/R(2015)2 (Internet), p.37 - 43, 2015/06

The Ministry of Education, Culture, Sports, Science, and Technology of Japan launched a Working Party to review research and development (R&D) on Partitioning and Transmutation (P&T) technology using an Accelerator Driven System (ADS), and issued an interim report in November, 2013. Although P&T concept with ADS, called Double-strata Fuel Cycle, had been regarded as a backup option of that with FBR, the Working Party recommended to promote the R&D phase of this technology to a principle demonstration stage. The Working Party recommended to facilitate the R&D toward the Transmutation Experimental Facility of J-PARC, though further technical evaluation was requested to start the construction. The Working Party also recommended to consistently facilitate R&D on partitioning process, dedicated transmutation fuel and its cycle. A consolidated roadmap toward the realization of this technology was also discussed

Journal Articles

Oxygen chemical diffusion coefficients of (Pu,Am)O$$_{2}$$ fuels

Watanabe, Masashi; Matsumoto, Taku*; Kato, Masato

NEA/NSC/R(2015)2 (Internet), p.376 - 380, 2015/06

no abstracts in English

Journal Articles

Thermal and mechanical properties of UO$$_{2}$$ and PuO$$_{2}$$

Kato, Masato; Matsumoto, Taku

NEA/NSC/R(2015)2 (Internet), p.162 - 167, 2015/06

Uranium and plutonium mixed oxide is base material for minor actinide (MA)-bearing MOX fuels. It is important to evaluate basic properties of UO$$_{2}$$ and PuO$$_{2}$$ as fundamental aspects of MA-bearing MOX fuel development. Especially, heat capacity and thermal conductivity of UO$$_{2}$$ and PuO$$_{2}$$ are important data to analyze thermal behaviors depending on Pu content. However, the data of PuO$$_{2}$$ is limited, and it is difficult to understand the mechanism of temperature dependence on their properties. The (Cv+Cd) of UO$$_{2}$$ and PuO$$_{2}$$ is almost same. The analysis results showed that the Schottky term of PuO$$_{2}$$ is 1.5 times as larger as that of UO$$_{2}$$. The thermal conductivity was analyzed by Slack equation. The calculation results showed that the thermal conductivity of PuO$$_{2}$$ was higher than that of UO$$_{2}$$. The relationship between mechanical and thermal properties was described, and the heat capacity and thermal conductivity were analyzed.

Journal Articles

Design study of accelerator-driven system for minor actinide transmutation in JAEA

Tsujimoto, Kazufumi; Nishihara, Kenji; Takei, Hayanori; Sugawara, Takanori; Iwamoto, Hiroki; Sasa, Toshinobu

NEA/NSC/R(2015)2 (Internet), p.254 - 261, 2015/06

The Japan Atomic Energy Agency (JAEA) has been conducting the research and development (R&D) on accelerator-driven system (ADS) as a dedicated transmutation system of long-lived radioactive nuclides. The ADS proposed by JAEA is a lead-bismuth eutectic (LBE) cooled fast subcritical reactor with thermal output of 800 MW. For ADS to play important roles in the nuclear fuel cycle, several critical issues have to be resolved. The critical issue in the design of the ADS is the engineering feasibility of the beam window for the high power spallation target. Although a feasible concept of the beam window for the ADS was proposed in our previous work. To mitigate the thermal load of the beam window not only in the normal operation but also in the transient situations, the R&D for the mechanism of reactivity adjustment and the accelerator design have been performed in JAEA.

Journal Articles

Recent progress and future R&D plan of nitride fuel cycle technology for transmutation of minor actinides

Hayashi, Hirokazu; Nishi, Tsuyoshi; Takano, Masahide; Sato, Takumi; Shibata, Hiroki; Kurata, Masaki

NEA/NSC/R(2015)2 (Internet), p.360 - 367, 2015/06

Uranium-free nitride fuel was chosen as the first candidate for transmutation of long-lived minor actinides (MA) using accelerator-driven system (ADS) under the double strata fuel cycle concept by Japan Atomic Energy Agency (JAEA). The advantages of nitride fuel are good thermal properties and large mutual solubility among actinide elements. A pyrochemical process is proposed as the first candidate for the reprocessing of the spent nitride fuel, because this technique has some advantages over aqueous process, such as the resistance to radiation damage, which is an important issue for the fuels containing large amounts of highly radioactive MA. This paper overviews the recent progress and future R&D plan of the study on the nitride fuel cycle technology in JAEA.

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