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Journal Articles

Conceptual design study and evaluation of advanced fuel fabrication systems in the feasibility study on commercialized FR fuel cycle in Japan

Namekawa, Takashi; Kawaguchi, Koichi; Koike, Kazuhiro; Haraguchi, Shingo; Ishii, Satoru

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10

New concepts of future fabrication system for low decontaminated transuranium (TRU) fuel was designed. It is essential to establish a remote fabrication system in the hot cell, because materials with high levels of radiation and high generation of heat are handled in the system. The configuration of the present systems including aspects related to economy was clarified through the conceptual design study. Technical feasibility of each concepts is follwiong. For oxide fuels, the simplified pelletizing method has a high technical feasibility for the process, and its expected practical use is possible at early stage, because this method is based on wealth results of a conventional method. The sphere-pack method has the advantage of lesser dispersion of the fine powder due to the use of solution and granule in the process. However this system will shoulder additional cost for the liquid waste treatment process due to need dispose of a large bulk of process liquid waste. The vipack method has the possibility of economical improvement if simplification of the process can be achieved. However this system has some problems for quality assurance etc. For the casting method of metal fuel, high economical efficiency is generally expected of small-scale facilities, although verification of fabrication of the TRU alloy slug is required. For nitride fuel, technology developments for N-15 enrichment and recycling, and nitride conversion process etc. In particular, for coated particle fuel fabrication, crucial technology developments are required on coating and assembly process.

Journal Articles

Design study and evaluaion of advanced fuel fabrication systems for FBR fuel cycle

Kawaguchi, Koichi; Namekawa, Takashi; Suzuki, Yoshihiro; Haraguchi, Shingo*

Proceedings of 13th International Conference on Nuclear Engineering (ICONE-13) (CD-ROM), 7 Pages, 2005/05

The conceptual design study for advanced FBR fuel fabrication system has been performed for the purpose that the feature of small-scale fabrication system in the transition stage from LWR to FBR fuel cycle. On the small-scale of 50 ton heavy metal per year fabrication system, dry type fabrication systems have superior cost performance than the wet type, although waste amount is larger.

JAEA Reports

Thermal-hydraulic analysis of plant dynamics test (II) SSC-L input manual for PLANDTL

Hayakawa, Hiroki*; Haraguchi, Tetsuharu*; Tanigawa, Shingo*

PNC TN9520 89-007, 499 Pages, 1989/03

PNC-TN9520-89-007.pdf:9.05MB

In the studies using PLANDTL, it would be planned to conduct the LOPI simulation experiment, the plant-wide natural circulation experiment, the DHX operational transient experiment, and so on. The goal of these R&D is to establish an assessment method for plant dynamics and to propose some design considerations on core conditions for the achievement of inherent safety features, passive decay heat removal capability. SSC-L (Super System Code - Loop Version) is to be as the main code in these studies and is used for the PLANDTL design analysis through test analysis. SSC-L is the most advantageous computational tool because the code is designed to analyze various kinds of transients and has been widely used for the safety analysis of LMFBR. In the first step of the plant dynamics tests, model development and modification of SSC-L has been achieved, and new models for PLANDTL are installed because the PLANDTL has the unique system and components to simulate LOPI conditions. After the modification and the experience of SSC-L application, we have made the input manual to conduct timely the pre- or post-analysis for the plant dynamics tests. The present document consists of the items corresponding to the various test conditions in order to quickly generate the input data.

JAEA Reports

Thermal-hydraulic analysis of plant dynamics test predictive analysis using SSC-L

*; Haraguchi, Tetsuharu*; *; Tanigawa, Shingo*; Yamaguchi, Katsuhisa

PNC TN9410 88-107, 121 Pages, 1988/09

PNC-TN9410-88-107.pdf:4.84MB

In the studies using PLANDTL, it would be planned to valid the thermal-hydraulic analysis codes which were developed each for whole system, plenum and subassembly, and also to evaluate the reactor plant in the future using these codes. SSC-L is to be as the main code in these studies and is used for design analysis through test analysis. In the first step of this study, model development and modification of SSC-L has been achieved for PLANDTL and predictive analyses have been applied as to validate the models and examine the design of PLANDTL. The estimated transient curves have been obtained about flow rate and temperatures at subassembly and loop of PLANDTL. As a result, the design conditions have been given to be able to perform the programmed tests. It have been validated that the conditions of tests would be within the design value, and the characteristics of PLANDTL and operational conditions have been obtained from the predictive analyses using design data of the plant. The modification and validation of SSC-L will be applied using the results of various kinds of functional tests, and test analyses will be performed in future.

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