Published September 2020 | Version v1
Journal article

A Program for High Temperature Structural Design Evaluation According to ASME B&PV

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

A structural integrity evaluation program (STEP) was developed for high temperature design evaluation according to the ASME Boiler and Pressure Vessel Code, Section III, Division 5 for high-temperature reactors. The program computerizes the evaluation procedure for primary stresses (HBB-3220) and for strain and creep-fatigue damage (HBB-T). In the evaluation, the material properties and isochronous curves for the candidate materials presented in Section II - Part D and HBB-T were computerized for high-temperature reactors. The program also computerized the weldment evaluation procedures and corresponding material properties. The program increases the efficiency of high-temperature reactor design and eliminates human error in complex hand calculation. The evaluation results from the STEP for single-cycle-type load were compared with those obtained using manual calculation with Microsoft Excel to verify the efficiency and reliability of STEP evaluations were efficient and reliable.

Additional details

Publishing Information

Journal Title
Transactions of the Korean Society of Mechanical Engineers. A
Journal Volume
44
Journal Issue
9
Series
14 refs, 10 figs, 7 tabs
Journal Page Range
p. 631-641
ISSN
1226-4873