反应堆压力容器钢辐照脆化的温度依赖性研究

Effect of Irradiation Temperature on Irradiation Embrittlement of Reactor Pressure Vessel Steel

  • 摘要: 针对低铜(Cu的含量≤0.072%)反应堆压力容器(RPV)钢的辐照脆化效应,分析近20年高通量工程试验堆(HFETR)和岷江试验堆(MJTR)的26次中子辐照试验结果,重点研究了辐照温度对RPV钢辐照脆化的影响。结果表明,辐照温度是影响RPV钢辐照损伤程度的重要因素之一,它能在宏观上决定材料性能退化的速率。应用美国RG1.99-3模型预估RPV钢低温辐照效应具有较高的可靠性,辐照脆化预估值与试验实测值吻合较好;当辐照温度在200~240 ℃之间时,温度对韧脆转变温度增量(ΔDBTT)影响最大;当辐照温度高于260 ℃时,温度对 RPV 钢辐照脆化的影响明显减小。辐照温度与ΔDBTT的关系符合阿伦尼乌斯定律。本文研究为国产压力容器的设计制造及老化和运行管理提供更多参考依据。

     

    Abstract: As the largest and non-replaceable key component of a nuclear power plant, the structural reliability of the reactor pressure vessel (RPV) is extremely important throughout its entire service life. It not only concerns whether the reactor can operate safely, but also involves the issue of extending the lifespan of the reactor until later stages of operation. Low Cu materials (≤0.072%) are used for RPV steel to reduce the radiation embrittlement caused by Cu. However, the material performance degradation of the component is still inevitable in the long-term high-energy neutron irradiation environment, mainly manifested as an increase in material brittleness and a decrease in fracture toughness caused by irradiation. The irradiation temperature and the neutron fluence level experienced are the main external variables that cause this degradation process. To analyze the effect of irradiation temperature on RPV steel, this paper summarized 26 neutron irradiation tests conducted in HFETR and MJTR over the past 20 years, analyzed the experimental data and explored the relationship between changes in irradiation temperature and the degree of irradiation embrittlement of RPV steel. The results indicate that irradiation temperature can macroscopically determine the rate of material performance degradation. The experimental data analysis shows that the increase in ductile-to-brittle transition temperature (ΔDBTT) is influenced by both neutron fluence and irradiation temperature. At a constant neutron fluence level, higher irradiation temperatures reduce the degree of material embrittlement; Whereas at a fixed temperature, higher neutron fluence leads to more severe embrittlement. At an irradiation temperature of 200 ℃ and a neutron fluence level of 9.7×1018 cm−2, the ΔDBTT is 98 ℃. At an irradiation temperature of 270 ℃ and a neutron fluence level of 9.6×1018 cm−2, the ΔDBTT is 34 ℃. When the irradiation temperature is 240 ℃ and the neutron fluence reaches 2.9×1019 cm−2, the ΔDBTT increases to 127 ℃. However, when the irradiation temperature remained at 240 ℃ but the neutron fluence decreased to 1.5×1019 cm−2, the ΔDBTT drops to only 49 ℃. Therefore, under the same irradiation temperature conditions, a decrease in neutron fluence leads to a corresponding reduction in ΔDBTT. As irradiation temperature decreases and neutron fluence increases, the ΔDBTT of RPV steel rises more significantly, resulting in a more pronounced irradiation embrittlement effect. When applying the RG1.99-2 model, a temperature coefficient correction is required, but this introduces considerable error and thus it is not recommended for standalone use. The RG1.99-3 model demonstrates high reliability in predicting low-temperature irradiation effects on RPV steels, with predicted irradiation embrittlement values closely matching experimental measurements. Therefore, the RG1.99-3 model is priority recommended. The influence of temperature on ΔDBTT is most significant when the irradiation temperature ranges between 200-240 ℃. When the irradiation temperature exceeds 260 ℃, the impact of temperature on material irradiation response becomes significantly reduced. Within the range of 200-300 ℃, the relationship between ΔDBTT and irradiation temperature for RPV steel follows the typical Arrhenius law.

     

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