反应堆压力容器材料辐射损伤模拟：多尺度方法

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-09-23 DOI:10.1016/j.nucengdes.2025.114415

Genshen Chu , Dandan Chen , Kang Zou , Xu Lu

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引用次数: 0

摘要

反应堆压力容器（RPV）是反应堆生命周期内唯一不能更换的核心设备。辐射脆化是RPV钢的主要性能问题，富cu团簇的析出是导致RPV钢脆化的主要原因之一。本文建立了多尺度模型，并开发了其仿真软件MISA，模拟了从初级缺陷产生到缺陷长期演化和宏观脆化冲击的演化过程，可为反应堆材料的研究与开发提供有效参考。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

Radiation damage simulation of reactor pressure vessel material: A multi-scale approach

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Radiation damage simulation of reactor pressure vessel material: A multi-scale approach

RPV (reactor pressure vessel) is the only core equipment that cannot be replaced during the life of the reactor. Radiation embrittlement is its main performance issue, and the precipitation of Cu-rich clusters is one of the main reasons for the embrittlement of RPV steel. In this paper, the multi-scale model is established and its simulation software MISA is developed for simulating evolution from primary defect generation to long-term evolution of defects and macro embrittlement impact, which can provide effective reference for the research and development of reactor materials.

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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.