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首页> 美国政府科技报告 >RELAP5-7: Demonstrating Seven-Equation, Two-Phase Flow Simulation in a Single-Pipe, Two-Phase Reactor Core and Steam Separator/Dryer.
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RELAP5-7: Demonstrating Seven-Equation, Two-Phase Flow Simulation in a Single-Pipe, Two-Phase Reactor Core and Steam Separator/Dryer.

机译：RELap5-7：在单管，两相反应堆堆芯和蒸汽分离器/干燥器中演示七方程，两相流模拟。

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The RELAP-7 code is the next generation nuclear reactor system safety analysis code being developed at the Idaho National Laboratory. RELAP-7 will become the main reactor systems toolkit for the Risk-Informed Safety Margin Characterization Pathway of the Light Water Reactor Sustainability (LWRS) Program and the next generation tool in the RELAP reactor safety/systems analysis application series (i.e., the replacement for RELAP5). The code is being developed based on Idaho National Laboratory's modern scientific software development framework MOOSE (i.e., the Multi-Physics Object-Oriented Simulation Environment). The RELAP-7 thermal hydraulics systems analysis code employs a seven-equation, two-phase flow model, which treats each phase as being compressible and does not assume pressure equilibrium between phases. This physically motivated model exhibits full thermodynamic and mechanical nonequilibrium and has real characteristics, is well-posed, and is hyperbolic. Both phases are compressible to enable handling of wave propagation, bubble collapse, and other key phenomena occurring in light water nuclear reactors, either in normal or offnormal operation. An additional advantage of utilizing well-posed governing equations for multiphase flow is they can be strictly verified like any modern computational fluid dynamics models.

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