核电工程用冲击试验标准对比分析

Comparative Analysis on Impact Test Standards for Nuclear Power Engineering

我国核电工程冲击试验通常采用GB/T 229-2007和ASTM E23-2007a两种标准,以核电工程常用的SA-508Gr.3Cl.1钢和SA-182F316LN钢为研究对象,从冲击吸收能量和韧脆转变温度两方面对比分析了两种标准的差异。结果表明:GB/T 229-2007更严格,按此标准测得的冲击吸收能量比按照ASTM E23-2007a测得的要低;当SA-508Gr.3Cl.1钢的试验温度高于韧脆转变温度时,采用两种标准测得的冲击吸收能量差值均随温度升高而增大;当温度低于韧脆转变温度时,采用两种标准测得的冲击吸收能量较接近;SA-182F316LN钢在试验温度范围内,按照ASTM E23-2007a测得的冲击吸收能量均比按照GB/T 229-2007测得的要高,且在-80℃两者差别最大。建议在充分积累核电工程材料冲击性能数据的基础上,逐步采用GB/T 229-2007进行核电材料冲击性能评价。

Two standards are usually adopted in impact test of nuclear power engineering in China:GB/T229-2007 and ASTM E23-2007 a.Taking SA-508 Gr.3 Cl.1 steel and SA-182 F316 LN steel commonly used in nuclear power engineering as research objects,the differences between the two standards were compared and analyzed from two aspects:impact absorption energy and ductile-brittle transition temperature.The results show that GB/T 229-2007 was more stringent.The impact absorption energy measured by this standard was lower than that measured by ASTM E23-2007 a.When the test temperature of SA-508 Gr.3Cl.1 steel was higher than the ductile-brittle transition temperature,the difference of impact absorption power measured by the two standards increased with the increase of temperature,and when the temperature was lower than the ductile-brittle transition temperature,the impact absorption power measured by the two standards was close.The impact absorption energy of SA-182 F316 LN steel measured by ASTM E23-2007 awas higher than that measured by GB/T 229-2007 in the test temperature range,and the difference between them was the greatest at-80 ℃.It is suggested that GB/T229-2007 should be gradually used to evaluate the impact performance of nuclear power materials on the basis of fully accumulating impact performance data of nuclear power engineering materials.