wwer - 440型核反应堆压力容器内部材料的热退火

Ivana Schnablová, R. Kopřiva, Ondřej Buršík, K. Rusňáková, A. Materna
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引用次数: 0

摘要

核电站长期运行超过60年的趋势要求保证其安全性和可靠性。延长反应堆压力容器(RPV)使用寿命的解决方案之一是热退火技术,该技术已得到验证,其在核工业中的应用主要是由于RPV无法交换。目前,对于不受监测程序监测的RPV内部,没有可比较的方法,它们的材料暴露在比RPV更强的中子通量中。本文提出了热退火作为一种可能的解决方案,以提供和重新建立足够的机械性能的RPV内部在操作过程中。根据已有的未辐照材料的结果,选择了两种退火方案,退火温度分别为550℃和600℃。通过对辐照材料进行热处理前后的硬度测试和静态断裂韧性测试,研究了热处理使材料的力学性能恢复到几乎与初始状态相对应的水平的可能性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
THERMAL ANNEALING OF WWER – 440 NUCLEAR REACTOR PRESSURE VESSEL INTERNALS MATERIAL
Current trend of long-term operation of NPP’s for more than 60 years requires assurance of its safety and reliability. One of the solutions how to extend service life of reactor pressure vessel (RPV) is thermal annealing, which became a verified technology and its application in nuclear industry was prompted mainly due to an inability of RPV exchange. At present time, there is no comparable method for RPV internals that are not monitored by surveillance program and their material is exposed to significantly more intense neutron flux than the RPV. Paper presents the thermal annealing as one of the possible solutions to provide and re-establish sufficient mechanical properties of RPV internals during the operation. According to previously obtained results of unirradiated material, two thermal annealing regimes for irradiated experimental material were selected based on the annealing temperatures of 550 and 600 °C. The possibility of recovery of mechanical properties to the level almost corresponding to the initial state by the thermal annealing was studied by hardness testing and static fracture toughness tests before and after the thermal annealing of irradiated material.
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