Analysis of the Main Steam Line Break Benchmark (Phase II) Using ANCK/MIDAC Code
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概要
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The three-dimensional (3D) neutronics and thermal-and-hydraulics (T/H) coupling code ANCK/MIDAC has been developed. ANCK/MIDAC consists of the 3D nodal kinetic code ANCK and the 3D drift flux T/H code MIDAC. In order to verify the adequacy of ANCK/MIDAC, the Phase II problem in the “OECD main steam line break benchmark (MSLB 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 The Phase II problem has a conservative condition that the control rod with the maximum worth is stuck in a fully withdrawn position throughout the transient. The simulation was performed using the core inlet temperatures and flow rates for 18 different regions, which were provided by the PSU best-estimate TRAC-PF1/NEM calculations. The comparison of the ANCK/MIDAC results with other participants’ results shows the excellent agreement on main core parameters. ANCK/MIDAC has good capability and reliability for the best-estimation code and a reasonable calculation time.
- 2008-01-25
著者
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AOKI Shigeaki
Mitsubishi Heavy Industries, Ltd.
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SUEMURA Takayuki
Mitsubishi Heavy Industries, Ltd.
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OGAWA Junto
Mitsubishi Heavy Industries, Ltd.
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TAKEDA Toshikazu
Osaka University
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Aoki Shigeaki
Mitsubishi Heavy Industries Ltd.
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Suemura Takayuki
Mitsubishi Heavy Industries Ltd.
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Ogawa Junto
Mitsubishi Heavy Industries Ltd.
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Takeda Toshikazu
Div. Of Sustainable Energy And Enviromental Engineering Graduate School Of Engineering Osaka Univ.
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Takeda Toshikazu
Department Of Sustainable Energy And Environmental Engineering Graduate School Of Engineering Osaka
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Takeda Toshikazu
Division Of Sustainable Energy And Environmental Engineering Graduate School Of Engineering Osaka Un
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AOKI Shigeaki
Mitsubishi Atomic Power Industries, Inc.
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