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Journal Articles

Correlations among FBR core characteristics for various fuel compositions

Maruyama, Shuhei; Oki, Shigeo; Okubo, Tsutomu; Kawashima, Katsuyuki; Mizuno, Tomoyasu

Journal of Nuclear Science and Technology, 49(6), p.640 - 654, 2012/06

 Times Cited Count:3 Percentile:24.98(Nuclear Science & Technology)

This study shows the good correlations in FBR core characteristics, and find out the mechanism of their correlations with the aid of sensitivity analyses. It has been clarified that Doppler coefficient turns to have the correlations with the other core characteristics by considering the constraint of the criticality requirement for fuel composition variations. The finding of the correlations makes easy to specify the ranges of core reactivity control and core safety properties which are important for core design in determining core specification and performance. It gives significant information for FBR core design in the transition stage. Moreover, as an application of the above-mentioned correlations, a simplified burnup reactivity index is developed for rapid and rational estimation of the core characteristic variations. By using this index and the correlations, the core characteristic variations can be estimated for various fuel compositions without repeating core calculations.

Journal Articles

Consideration of methods to determine an enrichment of commercial fast reactor fuel

Maruyama, Shuhei; Oki, Shigeo; Okubo, Tsutomu

Proceedings of 2011 International Congress on Advances in Nuclear Power Plants (ICAPP '11) (CD-ROM), p.1635 - 1643, 2011/05

In the situation that a variety of fuel composition is fed to FBRs during LWR-to-FBR transition stage, a special consideration on fuel reactivity and its loss by burnup is needed for each feeding fuel to keep criticality during operation period as prescribed. Suitable methods of determination of fuel enrichment will accomplish this without changing a pattern of fuel-loading (including number of loading fuel assembly). The choice of the method of enrichment determination affects the core characteristics which have to be controlled in core design. This paper describes some characteristics of the methods to determine an enrichment of fast reactor fuel from the core design points of view. Merits and demerits of these methods had been clarified in this study.

Journal Articles

Growth of large protein crystals by a large-scale hanging-drop method

Kakinouchi, Keisuke*; Nakamura, Tsutomu*; Tamada, Taro; Adachi, Hiroaki*; Sugiyama, Shigeru*; Maruyama, Mihoko*; Takahashi, Yoshinori*; Takano, Kazufumi*; Murakami, Satoshi*; Inoue, Tsuyoshi*; et al.

Journal of Applied Crystallography, 43(4), p.937 - 939, 2010/08

 Times Cited Count:4 Percentile:48.31(Chemistry, Multidisciplinary)

A method for growing large protein crystals is described. In this method, a cut pipette tip is used to hang large-scale droplets (maximum volume 200 $$mu$$l) consisting of protein and precipitating agents. A crystal grows at the vapor-liquid interface; thereafter the grown crystal can be retrieved by droplet-droplet contact both for repeated macroseeding and for mounting crystals in a capillary. Crystallization experiments with peroxiredoxin of ${it Aeropyrum pernix}$ K1(thioredoxin peroxidase, ApTPx) and hen egg white lysozyme demonstrated that this large-scale hanging-drop method could produce a large-volume crystal very effectively. A neutron diffraction experiment confirmed that an ApTPx crystal (6.2 mm$$^{3}$$) obtained by this method diffracted to beyond 3.5 ${AA}$ resolution.

Journal Articles

Study on FBR core concepts for the LWR-to-FBR transition period

Maruyama, Shuhei; Kawashima, Katsuyuki; Oki, Shigeo; Mizuno, Tomoyasu; Okubo, Tsutomu

Proceedings of International Conference on Advanced Nuclear Fuel Cycle; Sustainable Options & Industrial Perspectives (Global 2009) (CD-ROM), p.1548 - 1556, 2009/09

JAEA Reports

Coarse break-up of a stream of oxide and steel melt in a water pool (Contract research)

Moriyama, Kiyofumi; Maruyama, Yu; Usami, Tsutomu*; Nakamura, Hideo

JAERI-Research 2005-017, 173 Pages, 2005/08

JAERI-Research-2005-017.pdf:11.17MB

A series of experiments on the break-up of high temperature oxide and steel melt jets in a water pool was conducted. The objective was to obtain data for the jet break-up length and size distribution of the droplets produced by the jet break-up, and information on the influence of material properties. Also, we tried to obtain additional information giving a clue to the mechanism governing the melt jet break-up, such as flow intensity of the steam column surrounding the melt jet, and its relation with the droplet size. In the experiments, zirconia-alumina mixture and stainless steel melt jets with diameter $$sim$$17mm and velocity $$sim$$7.8m/s at the water surface were dropped into a deep (2.1m) or shallow (0.6m) water pool with various subcool. From the results of the present experiments and also by referring other experimental data from literature, we obtained empirical correlation equations for the jet break-up length, the fraction of jet broken-up in a shallow pool where the jet was not completely broken-up, and the droplet size.

Journal Articles

ITER engineering design

Shimomura, Yasuo; Tsunematsu, Toshihide; Yamamoto, Shin; Maruyama, So; Mizoguchi, Tadanori*; Takahashi, Yoshikazu; Yoshida, Kiyoshi; Kitamura, Kazunori*; Ioki, Kimihiro*; Inoue, Takashi; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 78(Suppl.), 224 Pages, 2002/01

no abstracts in English

Journal Articles

Vectorization and parallelization technique of block ILU preconditioning for unstructural problems

Osoda, Tsutomu*; Maruyama, Kunihide*; Washio, Takumi*; Doi, Shun*; Yamada, Susumu

Joho Shori Gakkai Rombunshi, 41(SIG8), p.92 - 100, 2000/11

no abstracts in English

JAEA Reports

Integrity assessment of test fuel assemblies of the High Temperature Engineering Test Reactor

Hayashi, Kimio; Shiozawa, Shusaku; Fukuda, Kosaku; Tsuruta, Harumichi; Ikawa, Katsuichi; *; ; Tobita, Tsutomu; Shiratori, Tetsuo; Akabori, Mitsuo; et al.

JAERI-M 90-115, 77 Pages, 1990/07

JAERI-M-90-115.pdf:2.65MB

no abstracts in English

Oral presentation

Experiment on melt jet break-up during LWR severe accidents

Moriyama, Kiyofumi; Maruyama, Yu*; Usami, Tsutomu*; Nakamura, Hideo

no journal, , 

no abstracts in English

Oral presentation

Consideration of methods to determine an enrichment of commercial fast reactor fuel

Maruyama, Shuhei; Oki, Shigeo; Okubo, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Basic research programs of vitrification technology for waste volume reduction, 65; Construction of MATRIX Database

Amamoto, Ippei; Oyama, Koichi; Nagano, Yuichi*; Nagao, Saichi*; Kitajima, Hideki*; Taneda, Naoki*; Maruyama, Tsutomu*; Sakai, Mitsuyoshi*; Nishikawa, Nobutaka*

no journal, , 

MATRIX database has been constructed to obtain experimental phase diagram using Interglad. It also possesses functions such as literature search, construction of computational phase diagrams by the thermodynamic method using FactSage as well as estimation of viscosity, density and/or electric resistance of certain glasses by neural network method.

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