压水堆运行中微小燃料棒破口的预测诊断研究

Study on prediction and evaluation method of micro fuel rod failures during PWR operation

  • 摘要: 压水堆核电厂运行中燃料棒破损会导致冷却剂放射性活度升高,不仅增加乏燃料存储、运输和处置的困难,严重时也会影响机组运行,因此需要及时对燃料破损情况开展诊断和检查。介绍了压水堆中裂变产物的产生和迁移机理,建立了通过裂变产物监测活度诊断燃料棒燃料破口的分析方法,结合某压水堆实际运行的典型案例识别出燃料棒微破口情况下不同类型裂变产物的释放特征,可以通过特征裂变产物的产生释放比(R/B)与衰变常数(λ)的拟合指数随时间变化来确定燃料破口演变过程,并通过停堆后啜漏检查对模型诊断结果进行确认。研究结果可以快速准确识别和定位破损燃料组件,降低破损燃料处理对核电厂大修工期影响。

     

    Abstract:
    Background During the operation of a nuclear power plant, fuel rod failure will lead to an increase in the radioactive activity in the primary coolant, increases the difficulty of storing, transporting and disposing of spent fuel. If the fuel failure has deteriorated to some degree, the reactor should be shut down within several hours to limit the release of fission products to the environment.
    Purpose Therefore, it is necessary to assess the status of fuel failure for the utilities as soon as possible.
    Methods In the paper, the generation and migration mechanism of fission products in the primary loops in pressurized water reactors has been introduced, and then one analytical method for diagnosing the status of fuel failure based on the measured fission product volume activity has been established. The characteristics of iodine and noble gas release from failed with tiny defects has been identified through one typical fuel failure cases. The evolution of fuel defect size can also be determined by the regression of release-to-birth (R/B) and the decay constant (λ) of fission products.
    Results The model diagnosis results have been confirmed by the sipping examination. The analysis of a typical failure case successfully reveals the characteristic release behavior of iodine and noble gases from small defects.
    Conclusions The proposed analytical method can help quickly identify and locate failed fuel assemblies, thereby reducing the impact of fuel failure treatment on the reactor overhaul period. This approach provides with a practical tool for timely assessment of fuel failure status and informed decision-making regarding reactor operation.

     

/

返回文章
返回