• 主题
高级搜索  >
历史搜索 清空历史
首页> 外文会议>Effects of radiation on nuclear materials and the nuclear fuel cycle >Final Results from the Crack Initiation and Arrest of Irradiated Steel Materials Project on Fracture Mechanical Assessments of Pre-lrradiated RPV Steels Used in German PWR
【24h】

Final Results from the Crack Initiation and Arrest of Irradiated Steel Materials Project on Fracture Mechanical Assessments of Pre-lrradiated RPV Steels Used in German PWR

机译：来自德国PWR预磨削的RPV钢的裂缝机械评估的辐照启动和遭受的裂缝启动和逮捕的最终结果

获取原文
页面导航
  • 摘要
  • 著录项
  • 相似文献
  • 相关主题

摘要

Pre-irradiated original reactor pressure vessel (RPV) materials covering all four German pressurized water reactors (PWR) construction lines were tested in the Crack Initiation and Arrest of Irradiated Steel Materials program to create a database of fracture toughness and arrest values for neutron fluences beyond the end of life range. The new database comprises data from both unirradiated and irradiated RPV base and weld materials generated by tensile, Charpy-V impact, fracture toughness Kjc, and crack arrest Kla tests. The test matrix consists of materials with optimized chemical composition and with high Copper or high Nickel content, respectively. Based on the generated and already existing data the RTNDT and the RTTO (Master Curve) concepts are applied with specific view on reference temperatures, transition temperature shifts, and on possible correlations be?tween the criteria used in both concepts. In this context the consequences of some influencing factors like type and chemical composition of the RPV steel, its manufacturing conditions, and the specimen type and size on the reference temperatures are discussed. Moreover, the test results are assessed with respect to the American Society of Mechanical Engineers (ASME) code and German Nuclear Safety Standards Commission safety standards. The crack arrest characteristics for these typical RPV materials are also determined in a twofold way by testing Compact Crack Arrest specimens and by evaluation of instrumented Charpy-V impact test data. The available results made a good point that crack arrest is a reliable phenomenon that doubtless exists. It is also shown that the obtained K]a data can be enveloped by applying the ASME K]c lower bound curve indexed by different reference temperatures. Finally, the results show that the used RPV materials are well designed in terms of material behavior under irradiated conditions and that optimized manufacture specifications are of great benefit particularly after long operation times.
机译：覆盖所有四种德国加压水反应器（PWR）建筑线的预辐射的原始反应器压力容器（RPV）材料在辐照钢材计划的裂纹启动和逮捕中进行了测试，以创建裂缝韧性和中子流量逮捕值的数据库寿命结束。新数据库包括来自未照射和辐照的RPV基碱和焊接材料，由拉伸，夏比 - 抗冲击，断裂韧性KJC和裂纹捕获KLA测试产生的数据。测试基质分别由具有优化化学成分和高铜或高镍含量的材料组成。基于所生成的和已经存在的数据，RTNDT和RTTO（主曲线）概念应用于参考温度，转变温度偏移的特定视图，并且在可能的相关性上是？在两个概念中使用的标准之间使用。在这种情况下，讨论了一些影响因素，如RPV钢的类型和化学成分，其制造条件和标本类型和参考温度的尺寸。此外，测试结果是关于美国机械工程师（ASME）守则和德国核安全标准委员会安全标准的评估。这些典型的RPV材料的裂纹停滞特性也通过测试紧凑的裂缝骤停标本并通过评估仪表的Charpy-V碰撞试验数据来以双重方式确定。可用的结果表明了裂缝逮捕是一种可靠的现象，无疑存在。还示出了所获得的K]数据可以通过施加由不同参考温度索引的ASME K] C下界曲线包围。最后，结果表明，在照射条件下的材料行为方面，使用的RPV材料精心设计，优化的制造规范特别有益，特别是经过长时间的操作时间。

著录项

相似文献

  • 外文文献
  • 专利
获取原文

客服邮箱：kefu@zhangqiaokeyan.com

京公网安备：11010802029741号 ICP备案号：京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有

  • 客服微信

  • 服务号