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Journal Articles

A Promising Gas-Cooled Fast Reactor Concept and its R&D Plan

Konomura, Mamoru; SAIGUSA, Toshiie; Mizuno, Tomoyasu; OHKUBO, Yoshiyuki*

Fast Spectrum Reactors, 0 Pages, 2003/00

In Feasibility Studies on Commercialized Fast Reactor (FR) Systems, examining about the subject of three gas cooled FR concepts, (1) carbon dioxide cooled FR using pin type fuel, (2) helium cooled FR using pin type fuel, (3) helium cooled FR using coated particle fuel, a promising concept has been selected from three concepts. From a viewpoint of economic competitiveness and ensuring safety, etc, "helium cooled FR using coated particle fuel" has been selected as a promising concept of gas cooled FR. About fuel assembly concept of helium cooled FR using coated particle fuel, block type vertical flow cooling concept with 2nd boundaries was also examined, other than horizontal flow cooling concept with directly cooling system. About selected helium cooled FR using coated particle fuel, it drew up R&D plan about the most important R&D items influencing on the feasibility of the design concept.

Journal Articles

Overall Plan and Progress Situation of "The Feasibility Study on Commercialized FR Cycle Systems"

Sagayama, Yutaka

Global 2003; International Conference on Atoms for Prosperity: Upda, 0 Pages, 2003/00

None

Journal Articles

Irradiation Performance of Uranium-Plutonium Mixed Nitride Fuel Pins in JOYO

; 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.

Journal Articles

A Promising Sodium-Cooled Fast Reactor Concept and its R&D Plan

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.

Journal Articles

Analysis of Curium in MOX Fuel Irradiated in Fast Reactor

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

Journal Articles

Conceptual design on an integrated metal fuel recycle system

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.

Journal Articles

3D Transport Theory Method Based on MOC for Analyzing Integral Dta of Transmutation

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.

Journal Articles

Advanced Fuel Cycle Stsyem and its R&D Plan in Japan

; 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

Journal Articles

Development of Geometrical Control Type Electrolyzer for Oxide-Electrowinning Process

Washiya, Tadahiro; Koizumi, Kenji; ; Aose, Shinichi

Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), 5 Pages, 2003/00

None

Journal Articles

Development of the Advanced Aqueous Reprocessing Process Technologies in CPF

Shibata, Atsuhiro; Nomura, Kazunori; ; Koyama, Tomozo

Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), 2251 Pages, 2003/00

None

Journal Articles

Operating Experience and Future Plan of the Operation Testing Laboratory in The Tokai Reprocessing Plant

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.

Journal Articles

Development of the Advanced Aqueous Reprocessing Process Technologies in CPF

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.

Journal Articles

Advanced Fuel Cycle System and its R&D Plan in Japan

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.

Journal Articles

Development of Geometrical Control Type Electrolyzer for Oxide-Electrowinning Process

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

Journal Articles

Vipac Fuel Fabrication for Irradiation Test of the FUJI Project

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

Journal Articles

Scenario study on fast reactor cycle deployment

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.

Journal Articles

Design Study on Minor Actinides Recovery for the NEXT Reprocessing

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.

Journal Articles

Corrosion Behavior of High Chromium Martensitlc Steel in LBE

Aoto, Kazumi; Nishi, Yoshihisa*; Furukawa, Tomohiro

Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) P.115-118, p.2113 - 2118, 2003/00

One of the vital issues to realize the lead-bismuth eutectics cooled fast reactor is to develop the proper protection of both structural and core materials from the LBE corrosion, especially at higher temperature than 600deg. In this work, a high chromium martensitic stainless steel (ASME P122) as a promising candidate of structural materials for LBE cooled FR was investigated to understand its corrosion behavior in stagnant LBE at 650deg under continuously controlled oxygen potentials. The specimens exposed to LBE up to 4,000h were analyzed by optical and chemical viewpoint to investigate the structure of the oxide layer and the behavior of main alloy elements in the steel. At higher temperature beyond the temperature range to from magnetite stably, the most outer iron-rich oxide was dissolved into LBE even under the proper controlled oxygen potential. And the diffusion area beneath the oxide was also dissolved into LBE after some time. However, based on the observation results, it is

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