高压堆芯熔体事故情景下压力边界破坏的材料特性和评估模型

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-05-07 DOI:10.1016/j.nucengdes.2025.114109

Christoph Bläsius , Jürgen Sievers , Annett Udoh , Stefan Weihe

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引用次数: 0

摘要

高压堆芯熔体事故情景下压力边界破坏的模拟需要特定的材料数据，而这些数据往往很少见。这项工作的重点是德国钢等级和合金用于kwu建造的反应堆在这个极端负载范围内的行为。在第一步中，描述了相关材料。简要介绍以往的工作。一系列的实验研究解决了一些悬而未决的问题，如合金800 （mod.）的短期蠕变，20mnmoni 5.5的撕裂行为，螺栓钢的松弛行为，高温氧化对断裂的影响，以及安全阀和安全阀接触面的行为。最后，提出了主要钢种的材料模型，并对其准确性和相关的不确定性进行了讨论。

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Material properties and models for the assessment of pressure boundary failure in high-pressure core melt accident scenarios

The simulation of pressure boundary failure in high-pressure core melt accident scenarios requires specific material data, which are often rare. This work focuses on the behavior of German steel grades and alloys used for KWU-built reactors in this extreme load range. In a first step, relevant materials are described. Previous work is presented in brief. A series of experimental studies addresses open questions regarding the material behavior in specific situations and for specific components, such as short-term creep of Alloy 800 (mod.), tearing behavior of 20 MnMoNi 5 5, relaxation behavior of bolt steels, influence of high-temperature oxidation on fracture, and behavior of contact surfaces in safety and relief valves. Finally, material models for the major steel grades are presented, verified, validated and their accuracy and associated uncertainties are discussed.

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.