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Takeda, Toshikazu*; Hamada, Yuzuru*; Kitada, Takanori*; Nishi, Hiroshi; Ishibashi, Junichi; Kitano, Akihiro
Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), p.1005 - 1010, 2003/00
A new 3-D transport calculation method taking into account the heterogeneity of fuel assemblies has been developed by combining the characteristics method and the nodal transport method. In the axial direction the nodal transport method is applied, and the characteristics method is applied to take into account the radial heterogeneity of fuel assemblies. The numerical calculations have been performed to verify 2-D radial calculations of FBR assemblies and partial core calculations. Results are compared with the reference Monte-Carlo calculations. A good agreement has been achieved. It is shown that the present method has an advantage in calculating reaction rates in a small region.
; Nomura, Shigeo; Ojima, Hisao; Funasaka, Hideyuki
Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), p.1290 - 1298, 2003/00
None
Washiya, Tadahiro; Koizumi, Kenji; Koizumi, Tsutomu; Aose, Shinichi
Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), 5 Pages, 2003/00
None
Shibata, Atsuhiro; Nomura, Kazunori; Koizumi, Tsutomu; Koyama, Tomozo
Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), 2251 Pages, 2003/00
None
Fukuda, Kazuhito; Tanabe, Yoji; Nojiri, Ichiro
Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), p.115 - 118, 2003/00
Operation Testing Laboratory (OTL) is an examination laboratory located in the Tokai Reprocessing Plant (TRP). It has provided many research results since 1972 and contributed to TRP in order to safety operation, troubleshooting, and new technology for future reprocessing. In this report, we present facility outline of the laboratory,the several experimental results and future plan.
Shibata, Atsuhiro; Nomura, Kazunori; Koizumi, Tsutomu; Koyama, Tomozo
Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), 2251 Pages, 2003/00
JNC has been developed the advanced aqueous reprocessing process. CPF is main hot test field for the reprocessing technologies using FR spent fuel. The hot tests have been restarted since last December. Results of dissolution, crystallization and simplified PUREX process tests were obtained through the first hot tests.
Nomura, Shigeo; Ojima, Hisao; Funasaka, Hideyuki
Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), 1290 Pages, 2003/00
Three candidate systems of spent fuel reprocessing integrated with fuel fabrication process,i.e.advanced aqueous,oxide electrowinning and metal electrorefining are studied as the Feasibility Study(FS)Phase-2 for advanced fast reactor fuel cycle.
Washiya, Tadahiro; Koizumi, Kenji; Koizumi, Tsutomu; Aose, Shinichi
Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), 773 Pages, 2003/00
None
Shigetome, Yoshiaki; Kono, Shusaku; Hellwig, C.*; Heimgartner, P.*
Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), p.1342 - 1347, 2003/00
None
Ono, Kiyoshi; Shiotani, Hiroki; Hirao, Kazunori
Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), 0 Pages, 2003/00
JNC started the feasibility study on commercialized Fast Reactor (FR) cycle system in 1999 and is estimating several promising FR cycle concepts. This report summarizes the analysis about the necessity of FR cycle deployment in Japan and in the world from a long-term viewpoint, by comparing "FR scenari" with "LWR once-through scenario" and "Pu recycling in LWR scenario". The necessity of FR cycle deployment in Japan and in the world was confirmed from viewpoints of effective utilization of uranium resource and reduction of environmental impact.
Koma, Yoshikazu; Takata, Takeshi; Sato, Koji; Sato, Koji
Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), p.1939 - 1944, 2003/00
As a part of the fasibility study on commercialized fast cycle systems,conceptual design study on aqueous recovery process of Am and Cm was conducted in order to choose the most promising method for future reprocessing plant. Process flow diagram,material balance and arrangement of equipment were made for the three alternative methods. The SETFICS is a solvent extraction using TRUEX solvent and DTPA-nitrate solution to obtain actinides (III) products wothout laight lanthanides. The MAREC is an extraction chromatography using a porous silica support. Amine extraction combines oxdation of actinides(III) to (IV) and extractionof polyanionic actinides(IV) complex into amine mixed solvent.Definite difference was not found in technical feasibility and safety of them at the present.Comparing waste generation and cost for apparatus, the MAREC process seems to have an advantage.