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首页> 外文期刊>Nuclear Technology >ANALYSIS OF THE OECD MAIN STEAM LINE BREAK BENCHMARK PROBLEM USING THE REFINED CORE THERMAL-HYDRAULIC NODALIZATION FEATURE OF THE MARS/MASTER CODE
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ANALYSIS OF THE OECD MAIN STEAM LINE BREAK BENCHMARK PROBLEM USING THE REFINED CORE THERMAL-HYDRAULIC NODALIZATION FEATURE OF THE MARS/MASTER CODE

机译:使用火星/主代码的改进的核心热液水化特征分析OECD主蒸汽线断裂基准问题

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摘要

The refined core thermal-hydraulics (T-H) nodalization feature of the MARS/MASTER code is used to generate a high-fidelity solution to the OECD main steam line break benchmark problem and to investigate the effects of core T-H nodalization. The MARS/MASTER coupling scheme is introduced first that enables efficient refined node core T-H calculations via the COBRA-Ⅲ module. The base solution is generated using a fine T-H nodalization consisting of fuel assembly-sized radial nodes. Sensitivity studies are performed on core T-H nodalization to examine the impacts on core reactivity, power distribution, and transient behavior. The results indicate that the error in the peak local power can be very large (up to 25%) with a coarse T-H nodalization because of the inability to incorporate detailed thermal feedback. A demonstrative departure from nucleate boiling (DNB) calculation shows no occurrence of DNB in this problem.
机译:MARS / MASTER代码的精炼核心热工水力(T-H)节点化功能用于为OECD主蒸汽管线断裂基准问题生成高保真度解决方案,并研究核心T-H节点化的影响。首先介绍了MARS / MASTER耦合方案,该方案可通过COBRA-Ⅲ模块进行高效的精炼节点核T-H计算。基本解决方案是使用由燃料组件大小的径向节点组成的精细T-H节点生成的。对核心T-H节点进行了敏感性研究,以检查对核心反应性,功率分布和瞬态行为的影响。结果表明,由于无法合并详细的热反馈,因此在粗略的T-H节点化时,峰值局部功率的误差可能非常大(高达25%)。从核沸腾(DNB)计算的证明偏离表明,在此问题中未发生DNB。

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