Development of a transient critical power ratio methodology for cycle specific BWR reload analysis

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
I. Clifford , K. Nikitin , A. Cherezov , A. Gorzel , M. Wolff , J. Dus , H. Ferroukhi
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引用次数: 0

Abstract

A new framework for generic hot channel transient CPR computations for modern BWR fuel assemblies has been developed with the goal of providing comprehensive independent safety assessments for BWR reload licensing analysis. TRAnsient Cpr analysis Tool (TRACT) is implemented in Python 3, and acts as a wrapper to calculate the critical CPR condition using TRACE as a hot channel code with initial and boundary conditions taken from upstream S3K simulations. TRACT supports subprocess-based (multi-processor) parallelism and MPI parallel execution, such that the transient CPR analyses for a typical BWR reload can be completed within minutes. Using object-oriented code design, new dryout correlations, fuel designs and even new hot channel codes can be introduced using a clean API, with minimal effort, and with little risk of breaking the existing code. The approach also makes it extremely simple to create unit tests for V&V. The V&V of TRACT is an ongoing process. While verification of the implemented correlations has been carried out, basic unit tests have been established, and selected validation has been conducted, this will be continuously extended in the future. A demonstration case has been presented to illustrate the capabilities of the code. Despite independent codes, models and methodologies, transient CPR predictions using TRACT are consistent with vendor results.
一种用于循环特定沸水堆重装分析的瞬态临界功率比方法的发展
为现代沸水堆燃料组件的通用热通道瞬态CPR计算开发了一个新的框架,目的是为沸水堆重装许可分析提供全面的独立安全评估。瞬态Cpr分析工具(TRACT)在Python 3中实现,并作为包装器使用TRACE作为热通道代码计算关键Cpr条件,其初始条件和边界条件来自上游S3K模拟。TRACT支持基于子进程(多处理器)的并行性和MPI并行执行,因此典型BWR重新加载的瞬态CPR分析可以在几分钟内完成。使用面向对象的代码设计,新的干干相关性、燃料设计甚至新的热通道代码都可以使用一个干净的API来引入,只需最少的努力,并且几乎没有破坏现有代码的风险。这种方法还使得为V&;V创建单元测试变得极其简单。TRACT的V&;V是一个持续的过程。虽然已经对实现的相关性进行了验证,建立了基本单元测试,并进行了选定的验证,但这将在未来不断扩展。给出了一个演示案例来说明代码的功能。尽管有独立的代码、模型和方法,但使用TRACT的瞬态CPR预测与供应商的结果一致。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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