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Sagayama, Yutaka
Global 2003; International Conference on Atoms for Prosperity: Upda, 0 Pages, 2003/00
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; Iwai, Takashi*; Arai, Yasuo*; Asaka, Takeo
Global 2003; International Conference on Atoms for Prosperity: Upda, 1694 Pages, 2003/00
Under the collaboration between JNC and JAERI, two uranium-plutonium mixed nitride fuel pins, whose smear densities were varied by fuel-to-cladding gap sizes, were irradiated in the experimental fast reactor JOYO. Linear heat rate, cladding mid-wall temperature, and burnup in peak were 75 kW/m, 906K, and 4.3 %FIMA, respectively. In order to evaluate nitride fuels for high burnup capability, the effect of fuel swelling behavior on irradiation performance was investigated. The larger smear density induced the greater cladding diameter increments. The wider gap size resulted in the more anisotropic deformations. Threshold temperature of fuel swelling was studied by thermal analysis using radial porosity and xenon retention profiles. To attain higher burnup, experimental results indicate that maximum fuel temperatures should be preferably lower than threshold temperatures of fuel swelling and that the detrimental effects of fuel pellet relocations need to be suppressed and accommodated.
Ichimiya, Masakazu; Mizuno, Tomoyasu; Konomura, Mamoru
Global 2003; International Conference on Atoms for Prosperity: Upda, 0 Pages, 2003/00
An innovative concept of sodium-cooled fast reactor, named JNC Sodium Cooled FR (JSFR) has been created through the Feasibility Study on Commercialized FR Cycle System, aiming at full satisfaction of the development targets. It is evaluated that JSFR possesses the highest potential in terms of technological feasibility to respond the diverse needs of society. JSFR supported by an appropriate fuel cycle is recognized as a promising candidate for the next generation nuclear energy system, such as GenerationIV system.
Osaka, Masahiko; Osaka, Masahiko; Koyama, Shinichi; Mitsugashira, Toshiaki
Global 2003; International Conference on Atoms for Prosperity: Upda, 0 Pages, 2003/00
Cm isotopes formed in irradiated MOX fuel in the experimental fast reactor JOYO were analyzed by applying a sophisticated radiochemical technique. Cm was isolated from the irradiated fuel by anion ion-exchange chromatography using a mixed medium of nitric acid and methanol. The isotopic ratio of Cm and its content were determined by thermal ionization mass spectroscopy and alpha-spectrometry, respectively. U, Pu, Am and Nd were also isolated and analyzed for the determination of the Cm content and burnup. The Cm content was less than 0.004 at.%, which is much smaller than that of PWR-MOX at 60 GWd/t. On the basis of the present analytical results, the transmutation behavior of Cm isotopes in a fast reactor was discussed from various viewpoints. Transmutation speeds of Cm isotopes were estimated; the speed for 246Cm, which is known to be a key nuclide in the transmutation of Cm, was smaller than the previously reported value. Transmutation behavior of each Cm isotope was also eval
; Fujii, Keiji; Inoue, Akira; Namba, Takashi; Sato, Koji
Global 2003; International Conference on Atoms for Prosperity: Upda, 0 Pages, 2003/00
The oxide electrowinning method is one of the non-aqueous reprocessing methods, and the construction of a compact, economical plant is expected in the combination with this reprocessing method and the fuel fabrication method utilizing the vibro-compaction process. For this reprocessing method, the rational process flow has been constructed on the basis of the existing technical information, from the viewpoint of the improvement of the economical efficiency. The conceptual design study of the main equipment concept and the equipment layout in main process cells on the basis of this process flow has been carried out from the viewpoint of the safety and operability. Then the number of equipments in this system and floor space of the process cells concerned with the economical efficiency have also been evaluated. In result, it has been seen that the capital cost by the future plant conceptual design study would be improved compared with the previous design, accordingly with the diminution
Sato, Koji; Fujioka, Tsunaaki; Nakabayashi, Hiroki; Kitajima, Shoichi; Yokoo, Takeshi*; Inoue, Tadashi*
Global 2003; International Conference on Atoms for Prosperity: Upda, 0 Pages, 2003/00
We have been performing the feasibility study on conceptual design for an integrated metallic fuel recycle plant of 38 tHM/y throughput. As a result of this study, the process concept was constructed, and the main equipment and devices were designed considering rationalixation,operationability, reduction of environmental impact and safety for the future commercialization. Furthermore, the image of the whole building included in cells was examined. In particular, the electrorefiner was enlarged from its current size and the cathode processor was improved from the current batch type to the continuation type to increase throughput. The plant was evaluated comprehensively. We confirmed that the major specifications for plant design would be satisfied. The economical cometitiveness of the plant has been evaluated.