Institute of Nuclear and New Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Collaborative Innovation Center for Advanced Nuclear Energy Technology, Tsinghua University, Beijing, 100084, China.
Institute of Nuclear and New Energy Technology, Beijing Key Laboratory of Fine Ceramics, Tsinghua University, Beijing, 100084, China.
Sci Rep. 2020 Jul 23;10(1):12330. doi: 10.1038/s41598-020-69282-7.
Maintaining the mechanical strength and hermetic reliability of metal-to-glass-ceramics electrical penetration assembly (MTGC-EPA) is a key concern for ensuring the pressure boundaries of nuclear power plants. The transient temperature change caused by power adjusting or accidents in High Temperature Reactor Pebble-bed Modules may affect the structural health of sealing glass-ceramics, even leading to radiation leakage. To evaluate whether the function could survive temperature variations during the service life, thermal cycling aging experiments were imposed to MTGC-EPA. A grating length-mismatched sensing method to monitor the residual strain, an important factor of glass-ceramics structural health, was demonstrated in real-time by femto-laser inscribed fiber Bragg grating (FBG) sensor during the curing process and thermal cycling aging. Scanning electron microscope (SEM) and leakage rate tests were carried out to obtain the comparisons of microstructure and hermeticity before and after the thermal cycling. The residual strain showed a slight growth trend with thermal cycles repetition and it persisted a high value (~ 4,000 με) reflected by both Bragg wavelength shift and spectrum shape. The grating length mismatched single FBG embedded in glass-ceramics was feasible to demodulate the temperature and strain simultaneously, and the embedded FBG method achieved the structural health monitoring of MTGC-EPA during thermal cycling aging with good accuracy and reliability. Combining with the results of SEM and leakage rate detecting, the structural health of MTGC-EPA was demonstrated to be capable to endure the severe thermal conditions in nuclear reactors.
保持金属-玻璃陶瓷电贯穿组件(MTGC-EPA)的机械强度和密封可靠性是确保核电厂压力边界的关键问题。高温堆卵石床模块中的功率调节或事故引起的瞬态温度变化可能会影响密封玻璃陶瓷的结构健康,甚至导致辐射泄漏。为了评估在使用寿命期间功能是否能够承受温度变化,对 MTGC-EPA 进行了热循环老化实验。在固化过程中和热循环老化过程中,通过飞秒激光刻写光纤布拉格光栅(FBG)传感器实时演示了一种用于监测残余应变的光栅长度失配传感方法,残余应变是玻璃陶瓷结构健康的重要因素。通过扫描电子显微镜(SEM)和泄漏率测试,获得了热循环前后微观结构和密封性的比较。残余应变随着热循环重复呈现出略微增长的趋势,并且通过布拉格波长移动和光谱形状都反映出它保持着高值(~4000 με)。嵌入玻璃陶瓷中的光栅长度失配单 FBG 可用于同时解调温度和应变,并且嵌入式 FBG 方法实现了 MTGC-EPA 在热循环老化期间的结构健康监测,具有良好的准确性和可靠性。结合 SEM 和泄漏率检测的结果,证明了 MTGC-EPA 的结构健康能够承受核反应堆中的恶劣热条件。