在核电厂分析评估模型中使用符合ASME标准的代码充分性方法

R. Schultz, G. Mesina
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摘要

今天使用的系统分析代码的开发是一项非常具有挑战性的任务,源于多种物理现象,特殊组件和控制系统的相互作用,特别是,在一个典型的设计基础事故场景中,广泛的热力学状态包络,包括水工作流体的单相和两相行为,在反应堆容器和蒸汽发生器中,对于间接循环压水堆系统,也对于直接循环沸水堆系统。导致当前系统分析规范的主要发展工作是在20世纪70年代到90年代之间完成的,今天,这些分析工具在世界各地被设计、提交设计以进行许可审查、建造和操作轻水反应堆核电站的组织使用。系统分析代码与高保真计算流体动力学(CFD)代码中使用的离散方程和闭包关系的形式不同,导致这两类代码中验证和验证(V&V)方程的技术相应不同。系统分析代码使用多年来开发的基本方法,并已得到监管机构的批准,而CFD代码使用ASME计算流体力学和传热代码的V&V标准中描述的高保真V&V技术。由于高保真CFD代码与系统分析代码的广泛使用,建议将这些工具的验证、确认和执行代码充分性评估的技术标准化,这些方法目前在美国核管理委员会的监管指南1.203中可用。概述了一种开始缩小用于V&V系统分析代码的基本方法与用于现代CFD代码的高保真技术之间差距的策略。假设差距可以缩小到一些“高保真”技术可以用于系统分析代码,从而提高系统分析代码的代码充分性确定过程的质量。
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Using Code Adequacy Methodologies in Confomance with ASME Standards for Nuclear Power Plant Analysis Evaluation Models
The development of the systems analysis codes in use today was a very challenging task, stemming from the interplay of multiple physical phenomena, special components and control systems, and particularly the wide thermodynamic state envelope for a typical design basis accident scenario that includes single and two-phase behavior of the water working fluid within both the reactor vessel and the steam generator for the indirect cycle pressurized water reactor systems and also for the direct cycle boiling water reactor systems. The major developmental work leading to the current systems analysis codes was performed between the 1970s through the 1990s—and today these analysis tools are used throughout the world by organizations that design, submit their designs for licensing reviews, build, and operate light water reactor nuclear power plants. Differences in form of the discretized equations and closure relationships used within the systems analysis codes versus those in higher-fidelity computational fluid dynamics (CFD) codes lead to correspondingly different techniques to verify and validate (V&V) the equations in these two classes of codes. Systems analysis codes use a fundamental approach which has been developed over the years and which has been approved by the regulatory agencies whereas the CFD codes use high-fidelity V&V techniques as described in the ASME V&V standards for computational fluid mechanics and heat transfer codes. Because of the wide usage of high-fidelity CFD codes together with systems analysis codes, it is advisable to normalize the techniques for verifying, validating, and performing code adequacy assessments of these tools within the methodology that is presently available in the U.S. Nuclear Regulatory Commission’s Regulatory Guide 1.203. A strategy to begin closing the gap between the fundamental approach used to V&V systems analysis codes and the high-fidelity techniques used for modern CFD codes is outlined. It is postulated that the gap can be closed to the extent that some of the “high-fidelity” techniques may be used for systems analysis codes and thus enhance the quality of the code adequacy determination process for systems analysis codes.
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