An integrated software platform of high-temperature design evaluation and defect assessment for a nuclear component and piping system subjected to high-temperature operation in creep regime has been developed. The program, called “HITEP_RCC-MRx,” is based on French nuclear grade high-temperature design code of RCC-MRx and enables a designer to conduct not only elevated temperature design evaluation but also elevated temperature defect assessment. HITEP_RCC-MRx consists of three modules: “HITEP_RCC-DBA,” which is programmed for the design-by-analysis (DBA) evaluation for class 1 pressure boundary components such as the pressure vessel and heat exchangers according to the RB-3200 procedures; “HITEP_RCC-PIPE,” which is programmed for the design-by-rule (DBR) evaluation according to the RB-3600 procedures; and “HITEP_RCC-A16,” which is programmed for high-temperature defect assessment according to the A16 procedures. The program has been verified with a number of related example problems on modules of DBA, Pipe, and A16. It was shown from the verification examples that integrated software platform of HITEP_RCC-MRx is capable of conducting three functions of an elevated temperature design evaluation for pressure boundary components and for piping, and an elevated defect assessment in an efficient and reliable way.
Skip Nav Destination
Article navigation
October 2019
Research-Article
HITEP_RCC-MRx Program for the Support of Elevated Temperature Design Evaluation and Defect Assessment
Hyeong-Yeon Lee,
Hyeong-Yeon Lee
Innovative System Technology
Development Division,
Korea Atomic Energy Research Institute,
989-111 Daedeok-daero,
Yuseong-gu,
Daejeon 34057, South Korea
Development Division,
Korea Atomic Energy Research Institute,
989-111 Daedeok-daero,
Yuseong-gu,
Daejeon 34057, South Korea
Search for other works by this author on:
Min-Gu Won,
Min-Gu Won
School of Mechanical Engineering,
Sungkyunkwan University,
Suwon-si, Gyeonggi-do 16419, South Korea
Sungkyunkwan University,
Suwon-si, Gyeonggi-do 16419, South Korea
Search for other works by this author on:
Nam-Su Huh
Nam-Su Huh
Department of Mechanical System
Design Engineering,
Seoul National University of
Science and Technology,
Seoul 01811, South Korea
Design Engineering,
Seoul National University of
Science and Technology,
Seoul 01811, South Korea
Search for other works by this author on:
Hyeong-Yeon Lee
Innovative System Technology
Development Division,
Korea Atomic Energy Research Institute,
989-111 Daedeok-daero,
Yuseong-gu,
Daejeon 34057, South Korea
Development Division,
Korea Atomic Energy Research Institute,
989-111 Daedeok-daero,
Yuseong-gu,
Daejeon 34057, South Korea
Min-Gu Won
School of Mechanical Engineering,
Sungkyunkwan University,
Suwon-si, Gyeonggi-do 16419, South Korea
Sungkyunkwan University,
Suwon-si, Gyeonggi-do 16419, South Korea
Nam-Su Huh
Department of Mechanical System
Design Engineering,
Seoul National University of
Science and Technology,
Seoul 01811, South Korea
Design Engineering,
Seoul National University of
Science and Technology,
Seoul 01811, South Korea
Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received May 18, 2018; final manuscript received May 22, 2019; published online July 17, 2019. Assoc. Editor: Andrew J. Duncan.
J. Pressure Vessel Technol. Oct 2019, 141(5): 051205 (13 pages)
Published Online: July 17, 2019
Article history
Received:
May 18, 2018
Revised:
May 22, 2019
Citation
Lee, H., Won, M., and Huh, N. (July 17, 2019). "HITEP_RCC-MRx Program for the Support of Elevated Temperature Design Evaluation and Defect Assessment." ASME. J. Pressure Vessel Technol. October 2019; 141(5): 051205. https://doi.org/10.1115/1.4043916
Download citation file:
Get Email Alerts
The Behavior of Elbow Elements at Pure Bending Applications Compared to Beam and Shell Element Models
J. Pressure Vessel Technol (February 2025)
Related Articles
A Serviceability Approach for Carbon Steel Piping to Intermittent High Temperatures
J. Pressure Vessel Technol (November,1996)
An Evaluation of Creep-Fatigue Damage for the Prototype Process Heat Exchanger of the NHDD Plant
J. Pressure Vessel Technol (October,2011)
Some Questions Regarding the Interaction of Creep and Fatigue
J. Eng. Mater. Technol (July,1976)
Conceptual Structure Design of High Temperature Isolation Valve for High Temperature Gas Cooled Reactor
J. Eng. Gas Turbines Power (November,2011)
Related Proceedings Papers
Related Chapters
Members in Bending
Design & Analysis of ASME Boiler and Pressure Vessel Components in the Creep Range
Pressure Testing
Process Piping: The Complete Guide to ASME B31.3, Third Edition
Piping Design
Power Boilers: A Guide to the Section I of the ASME Boiler and Pressure Vessel Code, Second Edition