Rodríguez-Prieto Alvaro, Primera Ernesto, Frigione Mariaenrica, Camacho Ana María
Department of Manufacturing Engineering, Universidad Nacional de Educación a Distancia (UNED), 28040 Madrid, Spain.
Department of Industrial Inspection and Technical Assistance, SGS Tecnos, 28042 Madrid, Spain.
Polymers (Basel). 2021 Mar 19;13(6):943. doi: 10.3390/polym13060943.
The degradation of polymeric components is of considerable interest to the nuclear industry and its regulatory bodies. The objective of this work was the development of a methodology to determine the useful life-based on the storage temperature-of acrylonitrile O-rings used as mechanical sealing elements to prevent leakages in nuclear equipment. To this aim, a reliability-based approach that allows prediction of the use-suitability of different storage scenarios (that involve different storage times and temperatures) considering the further required in-service performance, is presented. Thus, experimental measurements of Shore A hardness have been correlated with storage variables (temperature and storage time). The storage (and its associated hardening) was proved to have a direct effect on in-service durability, reducing this by up to 60.40%. Based on this model, the in-service performance was predicted; after the first three years of operation the increase in probability of failure (POF) was practically insignificant. Nevertheless, from this point on, and especially, from 5 years of operation, the POF increased from 10% to 20% at approximately 6 years (for new and stored). From the study, it was verified that for any of the analysis scenarios, the limit established criterion was above that of the storage time premise considered in usual nuclear industry practices. The novelty of this work is that from a non-destructive test, like a Shore A hardness measurement, the useful life and reliability of O-rings can be estimated and be, accordingly, a decision tool that allows for improvement in the management of maintenance of safety-related equipment. Finally, it was proved that the storage strategies of our nuclear power plants are successful, perfectly meeting the expectations of suitability and functionality of the components when they are installed after storage.
聚合物部件的降解是核工业及其监管机构相当关注的问题。这项工作的目的是开发一种方法,以确定用作防止核设备泄漏的机械密封元件的丙烯腈O形环基于储存温度的使用寿命。为此,提出了一种基于可靠性的方法,该方法能够在考虑进一步所需的服役性能的情况下,预测不同储存场景(涉及不同储存时间和温度)的使用适用性。因此,邵氏A硬度的实验测量值已与储存变量(温度和储存时间)相关联。事实证明,储存(及其相关的硬化)对服役耐久性有直接影响,可将其降低多达60.40%。基于该模型,预测了服役性能;在运行的头三年后,失效概率(POF)的增加实际上并不显著。然而,从这一点开始,尤其是从运行5年起,在大约6年时(对于新的和储存过的),POF从10%增加到20%。从该研究中可以验证,对于任何分析场景,既定的标准限值都高于核工业常规实践中考虑的储存时间前提。这项工作的新颖之处在于,通过像邵氏A硬度测量这样的无损检测,可以估计O形环的使用寿命和可靠性,因此它是一种有助于改进安全相关设备维护管理的决策工具。最后,事实证明我们核电站的储存策略是成功的,完全满足了部件在储存后安装时对适用性和功能性的期望。