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Evaluation of ductile-brittle transition temperature before and after neutron irradiation for RPV steels using small punch tests

机译:使用小冲孔试验评估RPV钢中子辐照前后的韧性-脆性转变温度

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摘要

Small punch (SP) tests were performed to evaluate the ductile-brittle transition temperature before and after a neutron irradiation of reactor pressure vessel (RPV) steels produced by different manufacturing (refining) processes. The results were compared to the standard transition temperature shifts from the conventional Charpy tests and the Master Curve fracture toughness tests in accordance with the American Society for Testing and Materials (ASTM) standard El921. Small punch specimens were taken from a 1/4t location of the vessel thickness and machined into a 10mm x 10mm x 0.5 mm dimension. The specimens were irradiated in the research reactors at Korea Atomic Energy Research Institute Nuclear Research Institute in the Czech Republic at the different fluence levels of about 290℃. Small punch tests were performed in the temperature range of RT to -196℃ using a 2.4 mm diameter ball. For the materials before and after irradiation, the small punch transition temperatures (T_(SP)), which are determined at the middle of the upper small punch energies, showed a linear correlation with the Charpy index temperature, T_(41 J). T_(SP) from the irradiated samples was increased with the fluence levels and was well within the deviation range of the unirradiated data. However, the transition temperature shift from the Charpy test (ΔT_(41 J)) shows a better correlation with the transition temperature shift (ΔT_(SP(E))) when a specific small punch energy level rather than the middle energy level of the small punch curve is used to determine the transition temperature. T_(SP) also had a correlation with the reference temperature (T_0) from the Master Curve method using a pre-cracked Charpy V-notched (PCVN) specimen.
机译:在通过不同制造(精炼)工艺生产的反应堆压力容器(RPV)钢的中子辐照之前和之后,进行了小冲孔(SP)测试以评估其韧性-脆性转变温度。将结果与常规夏比测试和根据美国材料试验学会(ASTM)标准El921进行的Master Curve断裂韧性测试的标准转变温度变化进行了比较。从容器厚度的1 / 4t位置取一些小的冲头样品,然后加工成10mm x 10mm x 0.5 mm的尺寸。样品以大约290℃的不同通量水平在捷克共和国的韩国原子能研究所核研究所的研究堆中辐照。在室温至-196℃的温度范围内,使用直径为2.4 mm的球进行小型冲压试验。对于辐照前后的材料,在较高的小冲头能量的中间确定的小冲头转变温度(T_(SP))与夏比指数温度T_(41 J)呈线性关系。辐照样品的T_(SP)随注量水平的增加而增加,并且很好地处于未辐照数据的偏差范围内。但是,当特定的小冲头能级而不是中间能级时,夏比试验的转变温度偏移(ΔT_(41 J))显示出与转变温度偏移(ΔT_(SP(E)))更好的相关性。小冲头曲线用于确定转变温度。 T_(SP)还与使用预破裂的夏比V型缺口(PCVN)标本的Master Curve方法的参考温度(T_0)相关。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2005年第19期|p.1799-1805|共7页
  • 作者单位

    Korea Atomic Energy Research Institute, 150 Deokjin-dong, Yuseong-gu, Daejeon 305-353, Republic of Korea;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

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