日本原子力学会 年会・大会予稿集
2009 Annual Meeting
セッションID: K42
会議情報
コード・ライブラリ開発
Analysis of Main Steam Line Break Benchmark Using the MARS/COREDAX Coupled Code
Analysis of Main Steam Line Break Benchmark Using the MARS/COREDAX Coupled Code
*Jaejun LeeNam Zin ChoSeungHoon Ahn
著者情報
会議録・要旨集 フリー

詳細
抄録
The three-dimensional (3D) neutronics and thermal- hydraulics (T/H) coupling code MARS/COREDAX has been developed. The 3D nodal kinetics code COREDAX is based on the Analytic Function Expansion Nodal (AFEN) method and the T/H code MARS is a best-estimate system analysis code that is based on the RELAP5/MOD3 and COBRA-TF codes. In order to verify the MARS/COREDAX code, the Phase II problem in the OECD main steam line break benchmark was analyzed. This MSLB benchmark has been defined in order to simulate the core response and the reactor coolant system response to a relatively severe steam line break accident condition. The comparison of the MARS/COREDAX results with other coupled codes will be presented.
著者関連情報
© 2009 Atomic Energy Society of Japan
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