混相流
Online ISSN : 1881-5790
Print ISSN : 0914-2843
ISSN-L : 0914-2843
【特 集】学会設立25周年記念特集(1)
原子力工学分野における混相流解析技術
(原子炉設計のための気液二相流解析技術の開発)
秋本 肇
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ジャーナル フリー

2012 年 26 巻 3 号 p. 266-272

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Research and development activities for two-phase analysis codes for nuclear reactor design and safety analyses have been reviewed focusing in recent twenty five years. For reactor safety evaluation, large-scale tests were performed to confirm effectiveness of ECCS in 1980’s and 1990’s. These test results were succeeded to so-called best-estimate codes such as RELAP5 , TRAC codes. Severe accident researches were performed in 1980’s and 1990’s and accident management methods were studied. Detailed simulation methods such as subchannel analysis, multi-dimensional analyses have been developed based on test results and computational technology enhancement in 1990’s and 2000’s. Future scope is summarized briefly.
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© 2012 日本混相流学会
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