A structural integrity evaluation program (STEP) was developed for the high temperature reactor design evaluation according to the ASME Boiler and Pressure Vessel Code (ASME B&PV), Section III, Rules for Construction of Nuclear Facility Components, Division 5, High Temperature Reactors, Subsection HB. The program computerized HBB-3200 (the design by analysis procedures for primary stress intensities in high temperature services) and Appendix T (HBB-T) (the evaluation procedures for strain, creep and fatigue in high temperature services). For evaluation, the material properties and isochronous curves presented in Section II, Part D and HBB-T were computerized for the candidate materials for high temperature reactors. The program computerized the evaluation procedures and the constants for the weldment. The program can generate stress/temperature time histories of various loads and superimpose them for creep damage evaluation. The program increases the efficiency of high temperature reactor design and eliminates human errors due to hand calculations. Comparisons that verified the evaluation results that used the STEP and the direct calculations that used the Excel confirmed that the STEP can perform complex evaluations in an efficient and reliable way. In particular, fatigue and creep damage assessment results are provided to validate the operating conditions with multiple types of cycles.

根据 ASME 锅炉和压力容器规范 (ASME B&PV)，第 III 部分，核设施部件建造规则，第 5 部分，高温反应堆，分节，为高温反应堆设计评估开发了结构完整性评估程序 (STEP) HB。该程序计算机化了 HBB-3200（根据高温服务中的主要应力强度分析程序设计）和附录 T (HBB-T)（高温服务中的应变、蠕变和疲劳评估程序）。为进行评估，第 II 部分 D 部分和 HBB-T 中介绍的材料特性和等时曲线被计算机化以用于高温反应堆的候选材料。该程序计算机化了焊件的评估程序和常数。该程序可以生成各种载荷的应力/温度时间历程，并将它们叠加起来进行蠕变损伤评估。该程序提高了高温反应器设计的效率，并消除了手工计算造成的人为错误。对使用 STEP 的评估结果和使用 Excel 的直接计算进行验证的比较证实，STEP 可以以高效可靠的方式执行复杂的评估。特别是，提供疲劳和蠕变损伤评估结果以验证具有多种类型循环的操作条件。对使用 STEP 的评估结果和使用 Excel 的直接计算进行验证的比较证实，STEP 可以以高效可靠的方式执行复杂的评估。特别是，提供疲劳和蠕变损伤评估结果以验证具有多种类型循环的操作条件。对使用 STEP 的评估结果和使用 Excel 的直接计算进行验证的比较证实，STEP 可以以高效可靠的方式执行复杂的评估。特别是，提供疲劳和蠕变损伤评估结果以验证具有多种类型循环的操作条件。