Abstract

The operating environment of nuclear reactors imposes extreme challenges on the materials from which the structures within and surrounding the reactor are constructed. Understanding the effects of exposure to this environment is critical for ensuring the safe long-term operation of these reactors. The Grizzly and BlackBear codes are being developed to model the progression of aging mechanisms and their effects on the integrity of critical structures. These codes take advantage of the capabilities of the MOOSE framework to solve the wide range of coupled physics problems that are encountered in predictive simulation of structural degradation. This paper provides an overview of these codes, with a specific focus on two capabilities relevant for light water reactor applications: reactor pressure vessel embrittlement and concrete degradation.

摘要

核反应堆的运行环境对建造反应堆内部和周围结构的材料提出了极大的挑战。了解暴露在这种环境中的影响对于确保这些反应堆的长期安全运行至关重要。正在开发 Grizzly 和 BlackBear 代码以模拟老化机制的进展及其对关键结构完整性的影响。这些代码利用 MOOSE 框架的功能来解决在结构退化的预测模拟中遇到的各种耦合物理问题。本文概述了这些规范，特别关注与轻水反应堆应用相关的两种能力：反应堆压力容器脆化和混凝土降解。