CIVA仿真在中国实验快堆主容器焊接结构超声检测探头选型中的应用

Application of CIVA Simulation in Ultrasonic Testing Probe Selection for Main Vessel Welded Structure of China Experimental Fast Reactor

  • 摘要: 中国实验快堆(CEFR)是我国第一座快中子反应堆,其建成意味着中国核能领域的重大进步。主容器作为包裹反应堆堆芯的第一道安全屏障,且与冷却剂钠液体直接接触,易出现冷却剂腐蚀和高温蠕变等缺陷裂纹,导致焊接结构失效,影响反应堆在服役期间的运行安全。超声检测作为无损检测的一种主要手段,可以作为针对CEFR主容器焊接结构检测的首选方法。本文以CEFR主容器焊接结构为检测对象,对待检试块进行检验分析,挑选出合适的超声检测探头。同时使用CIVA仿真软件对所选探头进行声束模拟及缺陷仿真计算。本文研究内容在一定程度上解决了CEFR主容器焊接结构的超声探头选型的难题,并为无损检测人员提供参考。

     

    Abstract: The China Experimental Fast Reactor (CEFR) represents a significant advancement in China’s nuclear energy sector, with its main vessel serving as the primary safety barrier enclosing the reactor core. However, the structural integrity of the main vessel’s welded components is susceptible to defects such as coolant-induced corrosion and high-temperature creep, posing potential safety risks during operation. While international efforts, including visual, ultrasonic, and eddy current inspections in reactors like France’s Phoenix-Ⅰ, Japan’s MONJU and India’s prototype fast reactor, have established in-service inspection protocols, research on nondestructive testing (NDT) for CEFR’s main vessel welds remains underdeveloped. Ultrasonic testing (UT), particularly phased array ultrasonic testing (PAUT), is recognized as a viable solution due to its penetration depth, adaptability to austenitic materials, and widespread application in nuclear facilities. Yet, traditional empirical probe selection methods often lead to inefficiencies, such as low detection accuracy and repeated trials. This study addresses the challenges in optimizing UT probe selection for CEFR’s main vessel welds by integrating simulation-based analysis. A comprehensive inspection technology analysis was first conducted on test blocks mimicking the welded structure, focusing on geometric parameters and acoustic properties. Subsequently, the CIVA simulation platform, developed by the French Atomic Energy and Alternative Energies Commission (CEA), was employed to model probe performance, including beam propagation and defect response. Key parameters such as probe frequency, aperture, and focal law configurations were systematically evaluated. The simulation results identify optimal probe parameters compliant with nuclear inspection standards, demonstrating CIVA’s capability to streamline probe selection and validate detection protocols. The findings reveal that conventional UT and PAUT probes exhibit limited detection rates for volumetric defects under standard gain settings. However, sensitivity improvements through gain compensation enhance defect characterization without compromising signal-to-noise ratios. While CIVA simulations account for material anisotropy in austenitic welds, real-world complexities—such as beam deviation, mode conversion, and scattering—introduce discrepancies between simulated and actual inspection outcomes. Consequently, post-simulation experimental validation is critical to ensuring detection reliability and minimizing false positives. In conclusion, this work establishes a simulation-driven framework for UT probe optimization in CEFR’s main vessel inspection, addressing gaps in existing methodologies. The proposed approach not only reduces economic and temporal costs associated with empirical probe selection but also provides actionable insights for NDT practitioners. Future efforts should prioritize experimental validation to reconcile simulation-observation mismatches and refine defect detection results, thereby advancing the safety and operational longevity of fast reactor systems.

     

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