Development of nuclear data processing and utilization system for innovative reactors

N. Yamano, A. Hasegawa, K. Kato, M. Igashira

研究成果: Conference contribution

2 被引用数 (Scopus)

抄録

A research and development (R&D) project on a nuclear data processing and utilization system was started in 2002 for a five-year plan for innovative nuclear energy systems such as innovative reactors and accelerator-driven systems. The nuclear data processing and utilization system is being developed to use on a PC-Linux server through the Internet, so that it has a graphic user interface (GUI) in order to easily utilize the system for various nuclear design studies in the innovative reactor development. The nuclear data processing and utilization system, which is able to handle JENDL-3.3, ENDF/B-VI, and JEFF-3 to generate point-wise and group-wise cross sections in several formats, has the capability to perform criticality and shielding benchmarks. A prototype system was developed in order to examine the operability of the user interface and discuss detailed specifications of the system. The system is expected to be a verification tool of nuclear data for development of innovative nuclear reactors, because cross-section generation with nuclear data and the various benchmarks for criticality and shielding problems can be easily performed.

本文言語English
ホスト出版物のタイトルInternational Conference on Nuclear Data for Science and Technology
ページ109-112
ページ数4
DOI
出版ステータスPublished - 2005 5月 24
外部発表はい
イベントInternational Conference on Nuclear Data for Science and Technology - Santa Fe, NM, United States
継続期間: 2004 9月 262004 10月 1

出版物シリーズ

名前AIP Conference Proceedings
769
ISSN(印刷版)0094-243X
ISSN(電子版)1551-7616

Other

OtherInternational Conference on Nuclear Data for Science and Technology
国/地域United States
CitySanta Fe, NM
Period04/9/2604/10/1

ASJC Scopus subject areas

  • 物理学および天文学(全般)

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