高温反应堆焊缝无损检测验收准则确定方法探究

Discussion on Determination of NDT Acceptance Criteria for Weld of Elevated Temperature Reactor

  • 摘要: 无损检测技术是核岛机械设备验收过程中保证焊接质量的重要手段。我国的核电厂机械设备焊缝无损检测验收准则主要源于国外的ASME、RCC-M等主流标准规范,国内缺乏相关的基础技术研究,尚不掌握制订验收准则的核心技术原理。本文在系统比较国内外无损检测验收标准规范的基础上,梳理了主要规范验收准则的沿袭关系,明确了验收标准的制定过程,总结了常见缺陷对焊接接头机械性能的影响,并结合基于断裂力学的缺陷评估方法和蠕变-疲劳损伤模型,提出了确定先进高温反应堆的焊缝无损检测验收标准的技术途径,对制定科学可靠、经济合理的高温堆型核级机械设备焊缝无损检测验收准则具有重要指导意义。

     

    Abstract: Non-destructive testing (NDT) is an important mean to ensure the welding quality of nuclear island machinery. The domestic welding acceptance standards of nuclear power plants are from foreign classic codes including ASME and RCC-M. However, basis principles of formulating the acceptance criteria are unclear. Based on systematical comparison of NDT acceptance criteria in major standards, it is found that the NDT acceptance standards in ASME and RCC-M are similar since RCC-M referred the system and principles of ASME, although there are several variations in detail. But the two codes both differ greatly from other welding acceptance criteria such as PNAE G-7-010-89 and ISO 5817. These acceptance criteria are mainly based on engineering experience at the time. This leads to inconsistencies in the definition of so-called “weld class systems” which were primarily developed based on concepts related to good workmanship but have little or no relation to the actual performance of the welded structure. The difference in the design standard system also affects the formulation of the NDT acceptance criteria. With the development of fracture mechanics theory and wide application of computer technology, flaw assessment methods based on fracture mechanics were developed. In the in-service inspection process, flaw assessment methods were used to replace the traditional welding quality assessment standards, while the innovation during the manufacturing is not tried in nuclear industry yet. In order to apply the flaw assessment methods to determine the welding acceptance criteria for non-destructive testing of high temperature reactors, following principles should be considered. First, there is no need to formulate different acceptance standards according to non-destructive testing methods, and only the nature of the defect itself, such as type, location, size, and quantity, should be distinguished. Second, considering the consistency of standard in use, the acceptance criteria should also be consistent with the welding evaluation method of design code. Finally, from the perspectives of fracture mechanics and fatigue damage, the influence of welding defects on the mechanical properties could be analyzed and summarized to set up the relationship between the volumetric defects and service life. Combined with the characteristics of whether the equipment can be replaced and whether it is easy to monitor in service, one can determine the acceptance limits with different margins. The technical principles of the method are instructively important for determining an advanced, reasonable, and economic welding NDT acceptance criteria of advanced reactors.

     

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