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Journal Articles

A Validation study of a neutronics design methodology for fast reactors using reaction rate distribution measurements in the prototype fast reactor Monju

Ohgama, Kazuya; Takegoshi, Atsushi; Katagiri, Hiroki*; Hazama, Taira

Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 8 Pages, 2019/05

Journal Articles

A Design study on a mixed oxide fuel sodium-cooled fast reactor core partially loading highly concentrated MA-containing metal fuel

Ohgama, Kazuya; Ota, Hirokazu*; Oki, Shigeo; Iizuka, Masatoshi*

Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 9 Pages, 2019/05

Journal Articles

Model verification and validation procedure for a neutronics design methodology of next generation fast reactors

Ohgama, Kazuya; Ikeda, Kazumi*; Ishikawa, Makoto; Kan, Taro*; Maruyama, Shuhei; Yokoyama, Kenji; Sugino, Kazuteru; Nagaya, Yasunobu; Oki, Shigeo

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 10 Pages, 2017/04

Journal Articles

Tradeoff analysis of metal-fueled fast reactor design concepts

Stauff, N. E.*; Ohgama, Kazuya; Aliberti, G.*; Oki, Shigeo; Kim, T. K.*

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 10 Pages, 2017/04

Journal Articles

Design study of a 750 MWe Japan sodium-cooled fast reactor with metal fuel

Ohgama, Kazuya; Ota, Hirokazu*; Ikusawa, Yoshihisa; Oki, Shigeo; Ogata, Takanari*

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6 Pages, 2017/04

JAEA Reports

Development of the versatile reactor analysis code system, MARBLE2

Yokoyama, Kenji; Jin, Tomoyuki; Hirai, Yasushi*; Hazama, Taira

JAEA-Data/Code 2015-009, 120 Pages, 2015/07

JAEA-Data-Code-2015-009.pdf:1.93MB

The second version of the versatile reactor analysis code system, MARBLE2, has been developed. A lot of new functions have been added inMARBLE2 by using the base technology developed in the first version (MARBLE1). Introducing the remaining functions of the conventional code system (JOINT-FR and SAGEP-FR), MARBLE2 enables one to execute almost all analysis functions of the conventional code system with the unified user interfaces of its subsystem, SCHEME. In particular, the sensitivity analysis functionality is available in MARBLE2. On the other hand, new built-in solvers have been developed, and existing ones have been upgraded. Furthermore, some other analysis codes and libraries developed in JAEA have been consolidated and prepared in SCHEME. In addition, several analysis codes developed in the other institutes have been additionally introduced as plug-in solvers. Consequently, $$gamma$$-ray transport calculation and heating evaluation become available. As for another subsystem, ORPHEUS, various functionality updates and speed-up techniques have been applied based on user experience of MARBLE1 to enhance its usability.

Journal Articles

Neutronics design of the low aspect ratio tokamak reactor, VECTOR

Nishitani, Takeo; Yamauchi, Michinori*; Nishio, Satoshi; Wada, Masayuki*

Fusion Engineering and Design, 81(8-14), p.1245 - 1249, 2006/02

 Times Cited Count:13 Percentile:30.44(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Proceedings of the 11th International Workshop on Ceramic Breeder Blanket Interactions; December 15 - 17, 2003, Tokyo, Japan

Enoeda, Mikio

JAERI-Conf 2004-012, 237 Pages, 2004/07

JAERI-Conf-2004-012.pdf:44.1MB

This report is the Proceedings of "the Eleventh International Workshop on Ceramic Breeder Blanket Interactions" which was held as a workshop on ceramic breeders Under the IEA Implementing Agreement on the Nuclear Technology of Fusion Reactors, and the Japan-US Fusion Collaboration Framework. In the workshop, information exchange was performed for designs of solid breeder blankets and test blankets in EU, Russia and Japan, recent results of irradiation tests, HICU, EXOTIC-8 and the irradiation tests by IVV-2M, modeling study on tritium release behavior of Li$$_{2}$$TiO$$_{3}$$ and other breeders, fabrication technology developments and characterization of the Li$$_{2}$$TiO$$_{3}$$ and Li$$_{4}$$SiO$$_{4}$$ pebbles, research on measurements and modeling of thermo-mechanical behaviors of Li$$_{2}$$TiO$$_{3}$$ and Li$$_{4}$$SiO$$_{4}$$ pebbles, and interfacing issues, such as, fabrication technology for blanket box structure, neutronics experiments of blanket mockups by fusion neutron source and tritium recovery system.

Journal Articles

Current status of the AGS spallation target experiment

Nakashima, Hiroshi; Takada, Hiroshi; Kasugai, Yoshimi; Meigo, Shinichiro; Maekawa, Fujio; Kai, Tetsuya; Konno, Chikara; Ikeda, Yujiro; Oyama, Yukio; Watanabe, Noboru; et al.

Proceedings of 6th Meeting of the Task Force on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-6), (OECD/NEA No.3828), p.27 - 36, 2004/00

no abstracts in English

Journal Articles

Development of supercritical pressure water cooled solid breeder blanket in JAERI

Akiba, Masato; Ishitsuka, Etsuo; Enoeda, Mikio; Nishitani, Takeo; Konishi, Satoshi

Purazuma, Kaku Yugo Gakkai-Shi, 79(9), p.929 - 934, 2003/09

no abstracts in English

JAEA Reports

Core neutronics module and database access module for intelligent reactor design system (IRDS)

Kugo, Teruhiko; Tsuchihashi, Keiichiro*; Nakakawa, Masayuki; Ido, Masaru*

JAERI-Data/Code 2000-011, p.138 - 0, 2000/02

JAERI-Data-Code-2000-011.pdf:7.41MB

no abstracts in English

JAEA Reports

Multi-dimensional design window search system using neural networks in reactor core design

Kugo, Teruhiko; Nakakawa, Masayuki

JAERI-Data/Code 2000-004, p.97 - 0, 2000/02

JAERI-Data-Code-2000-004.pdf:10.51MB

no abstracts in English

Journal Articles

Application of neural network to multi-dimensional design window search in reactor core design

; Nakakawa, Masayuki

Journal of Nuclear Science and Technology, 36(4), p.332 - 343, 1999/04

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Applicability of design window search procedure using neural network to neutronics

; Nakakawa, Masayuki

Proc. of Int. Conf. on the Phys. of Nucl. Sci. and Technol., 1, p.704 - 711, 1998/00

no abstracts in English

Journal Articles

Development of intelligent code system to support conceptual design of nuclear reactor core

; Nakakawa, Masayuki;

Journal of Nuclear Science and Technology, 34(8), p.760 - 770, 1997/08

 Times Cited Count:2 Percentile:75.74(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

SRAC95; General purpose neutronics code system

Okumura, Keisuke; *;

JAERI-Data/Code 96-015, 445 Pages, 1996/03

JAERI-Data-Code-96-015.pdf:12.94MB

no abstracts in English

Journal Articles

Design and techniques for fusion blanket neutronics experiments using an accelerator-based deuterium-tritium neutron source

Oyama, Yukio; Konno, Chikara; Ikeda, Yujiro; Maekawa, Fujio; Maekawa, Hiroshi; ; ; Nakamura, Tomoo; M.A.Abdou*; Bennett, E. F.*; et al.

Fusion Technology, 28(1), p.56 - 73, 1995/08

no abstracts in English

JAEA Reports

Development of thermal design method of rotating target for DT neutron source

; Ikeda, Yujiro; Kusano, Joichi

JAERI-M 94-016, 89 Pages, 1994/02

JAERI-M-94-016.pdf:2.1MB

no abstracts in English

JAEA Reports

Neutronics design of JMTR-LEU core

Nagaoka, Yoshiharu; Komukai, Bunsaku; ; Koike, Sumio; Saito, Minoru;

JAERI-M 92-098, 81 Pages, 1992/07

JAERI-M-92-098.pdf:1.81MB

no abstracts in English

JAEA Reports

26 (Records 1-20 displayed on this page)