CURRENT STATUS AND DEVELOPMENT OF CORE CALCULATION METHODOLOGY FOR SODIUM COOLED FAST REACTOR IN MITSUBISHI

摘要：

This paper presents current status and development of nuclear calculation methodology for sodium cooled fast reactor in Mitsubishi and two core design codes; an original two dimensional cell/lattice calculation code, PIJHEX and a thermal hydraulic calculation code, MIX-MKII. Mitsubishi Atomic Power Industries, Inc. developed several core design codes for Monju and JOYO and recently this activity continues still further for the next FBR in Japan. It is explained in this paper that the PIJHEX is confirmed to be valid from the comparison of Monte Carlo code and the examination on physical phenomenon in calculation results. Besides, the approach toward design and development of code system in Mitsubishi and MIX-MKII are introduced briefly.

作者: Kazumi Ikeda Hiroyuki Moriwaki Wataru Nakazato

作者单位: Mitsubishi FBR systems, Inc.34-17, Jingumae 2-Chome, Shibuya-ku, Tokyo,150-0001, Japan Mitsubishi Heavy Industries, Ltd.,1-1, Wadasaki-cho 1-chome, Hyogo-ku, Kobe,652-8585, Japan

会议类型: 国际会议

会议名称: 18th International Conference on Nuclear Engineering(第18届国际核能工程大会 ICONE 18)

会议地点: 西安

会议语种:英文

页码: 1-10

在线出版日期: 2010-05-17（万方平台首次上网日期，不代表论文的发表时间）