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Journal Articles

Corrosion study on cold crucible for pyrochemical reprocessing of spent nuclear fuel

Takeuchi, Masayuki; Arai, Yoichi; Kase, Takeshi; Koizumi, Tsutomu

Proceedings of International Symposium on EcoTopia Science 2007 (ISETS '07) (CD-ROM), p.1084 - 1088, 2007/11

Pyrochemical reprocessing methods using molten salt for spent nuclear fuel have been studied in the world, because of advantage over the nuclear weapons proliferation and cost benefit. However, electrowinning process, which is one of the processes in pyrochemical reprocessing method, includes severe corrosion environment. In this study, the efficacy of cold crucible in electrowinning process was experimentally discussed. We carried out the corrosion test of several metals in molten 2CsCl-NaCl with corrosive gases at 923 K to investigate the relationship between material temperature controlled by air cool and corrosion rate. As results, the corrosion rate of hastelloy alloy was less than 0.1 mm/y by cooling the material surface at 473 K and corresponds to 1/1000 of that at 923 K. In such way, the cold crucible gives the extreme improvement of corrosion, and this result gave promising prospect to solve the corrosion problem in electrowinning process.

Journal Articles

Uranium crystallization study with irradiated MOX fuel

Nomura, Kazunori; Nakahara, Masaumi; Yano, Kimihiko; Sano, Yuichi; Shibata, Atsuhiro; Washiya, Tadahiro

Proceedings of International Symposium on EcoTopia Science 2007 (ISETS '07) (CD-ROM), p.1058 - 1061, 2007/11

Journal Articles

Current status of chemical sputtering of graphite and related materials

Matsunami, Noriaki*; Nakano, Tomohide

Proceedings of International Symposium on EcoTopia Science 2007 (ISETS '07) (CD-ROM), p.321 - 322, 2007/11

Journal Articles

Some advanced technologies for low-level radioactive waste treatment in JAEA

Meguro, Yoshihiro; Tomioka, Osamu; Yamaguchi, Hiromi; Takahashi, Kuniaki

Proceedings of International Symposium on EcoTopia Science 2007 (ISETS '07) (CD-ROM), p.1043 - 1046, 2007/11

In order to lower the cost of the disposal of low-level radioactive waste, several waste treatment technologies, such as reduction of radioactive concentration in the waste, reduction in amount of the waste, and removal of harmful materials for the disposal, are essential. The authors have developed four waste treatment technologies; these are a supercritical CO$$_2$$ fluid decontamination method, a calcination method, a chemical reductive denitration method, and a steam reforming method in JAEA. It was demonstrated that these methods showed promise for the waste treatment.

Journal Articles

Basic knowledge on treating various wastes generated from practical operation of metal pyro-reprocessing

Nakayoshi, Akira; Kitawaki, Shinichi; Fukushima, Mineo; Kurata, Masaki*; Yahagi, Noboru*

Proceedings of International Symposium on EcoTopia Science 2007 (ISETS '07) (CD-ROM), p.1062 - 1066, 2007/11

Pyro-reprocessing is one of the promising reprocessing methods for recycling spent nuclear fuels generated from fast reactors. Comparing to the conventional aqueous-processes, following benefits are expected when introducing the pyro-reprocessing, such as reduction of environmental burden, enhancement of proliferation-resistant, enhancement of economical potential, efficient utilization of nuclear resources. The pyro-reprocessing will therefore become more attractive not only in developed countries regarding nuclear energy, but also in developing countries. As for reducing environmental burden, the most important subject is establishment of the nuclear fuel cycle, in which actinide elements are closed. Various kinds of intermediate waste which contains actinide elements are formed in the practical operation not only from the main steps of the pyro-reprocessing but also from related sub-streams.

Oral presentation

Power and particle control in JT-60SA to support and supplement ITER and DEMO

Sakurai, Shinji

no journal, , 

JT-60U will be modified as a fully superconducting coil tokamak JT-60SA. Divertor cassettes are introduced to be maintained by remote handling for high dose rate due to a substantial annual neutron production. A monoblock type carbon fibre composite divertor target will be used to withstand a heat load of 15 MW/m$$^{2}$$. All of the plasma facing components are water-cooled to handle heat load during 100s or more. Divertor heat load and pumping efficiency for an ITER-like configuration has been evaluated, using 2D plasma fluid (SOLDOR) and neutral Monte-Carlo (NEUT2D) code. In the simulation for the divertor with a "V-shaped corner" like as that in ITER, the plasma detachment occurs near the outer-strike point within the "V-shaped corner", as well as near the inner-strike point, which results in low peak heat flux density 5.8 MW/m$$^{2}$$ for the case with additional gas puff of 5 $$times$$ 10$$^{21}$$/s compared to 11.4 MW/m$$^{2}$$ for the case without "V-shaped corner".

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