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Journal Articles

FBR cycle development

Negishi, Hitoshi; Chatani, Keiji; Tanigawa, Shingo

Genshiryoku Nenkan 2008, p.53 - 61, 2007/09

The Japanese government assessed the result of "Feasibility Study on Commercialized FR Cycle System 2nd Phase" and a major concept that is the combination of a sodium cooled FBR (oxide fuel), an advanced aqueous reprocessing and a simplified pelletizing was selected. From now on, the JAEA invests the development resource to a major concept intensively, and aims to put it to practical use by new project, "FaCT". In "Monju", the plant improvement construction have been working on schedule, and the various tests for restart are advanced. The R&D results in "Monju" will be applied to FBR development near future. "Joyo" has been operated over 70,000 hours, and has provided the fields to develop FBR fuel & material. In addition, the external utilization of "Joyo" is enhancing now. FBR development is activating worldwide. The international cooperation under GIF, GNEP and INPRO and the research collaboration with America/France are carrying.

Journal Articles

Mechanical properties of small size specimens of F82H steel

Wakai, Eiichi; Otsuka, Hideo*; Matsukawa, Shingo; Furuya, Kazuyuki*; Tanigawa, Hiroyasu; Oka, Keiichiro*; Onuki, Somei*; Yamamoto, Toshio*; Takada, Fumiki; Jitsukawa, Shiro

Fusion Engineering and Design, 81(8-14), p.1077 - 1084, 2006/02

 Times Cited Count:11 Percentile:61.93(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Tempering treatment effect on mechanical properties of F82H steel doped with boron and nitrogen

Okubo, Nariaki; Wakai, Eiichi; Matsukawa, Shingo; Tanigawa, Hiroyasu; Sawai, Tomotsugu; Jitsukawa, Shiro; Onuki, Somei*

Materials Transactions, 46(8), p.1779 - 1782, 2005/08

 Times Cited Count:1 Percentile:16.76(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Heat treatment effects on microstructures and DBTT of F82H steel doped with boron and nitrogen

Okubo, Nariaki; Wakai, Eiichi; Matsukawa, Shingo*; Furuya, Kazuyuki; Tanigawa, Hiroyasu; Jitsukawa, Shiro

Materials Transactions, 46(2), p.193 - 195, 2005/02

 Times Cited Count:1 Percentile:16.76(Materials Science, Multidisciplinary)

no abstracts in English

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

Key design parameter study (II) for large scale-up fast breeder reactor; Optimizing analysis of inherent negative reactivity feedback effect (I); Analysis on thermal transformation of core support plate

*; Tanigawa, Shingo*; *; Yamaguchi, Katsuhisa; *; *; *

PNC TN9410 88-141, 159 Pages, 1988/09

PNC-TN9410-88-141.pdf:10.2MB

The structural analyses of the core support plate have been applied to study thermal transfomation behaviors and the differences of the movement by changing analytical model, under anticipated transient without scram (ATWS) conditions of FBR. The analyses have been performed for 1000 MWe class loop type fast breeder reactor using a structural analysis code FINAS. The thermal-hydraulic results, which have been performed to ATWS conditions using a plant system code, were used as the thermal boundary conditions to the calculation. The scope of the analyses included a whole section of reactor vessel and the dead load of core assemblies was also considered. Following results were obtained from these studies. (1)The thermal transformation of a upper core support plate can be evaluated according to the free expansion behavior owing to the temperature change of core support plate itself. (2)The radial restriction due to core subassemblies has much influence on the axial bend of the core support plate. (3)There are some differences to the transformation results between by the whole model and by the one dimensional model during the thermal transient is large. Another analysis will be needed, however, about the reactivity change according to the displacement of the core structure.

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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