HITEP_RCC-MRx Program for the Support of Elevated Temperature Design Evaluation and Defect Assessment

Author:

Lee Hyeong-Yeon1,Won Min-Gu2,Huh Nam-Su3

Affiliation:

1. Innovative System Technology Development Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon 34057, South Korea

2. School of Mechanical Engineering, Sungkyunkwan University, Suwon-si, Gyeonggi-do 16419, South Korea

3. Department of Mechanical System Design Engineering, Seoul National University of Science and Technology, Seoul 01811, South Korea

Abstract

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.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Reference19 articles.

1. Status of Fast Reactor Research and Technology Development;IAEA,2012

2. BPVC Section III, Rules for Construction of Nuclear Power Plant Components, Division 5, High Temperature Reactors;ASME,2017

3. Section I Subsection B, Class 1 N1RX Reactor Components;RCC-MRx,2018

4. BPVC Section III, Rules for Construction of Nuclear Power Plant Components, Division 1, Subsection NH Class 1 Components;ASME,2017

5. Comparison of Elevated Temperature Design Codes of ASME Subsection NH and RCC-MRx;Nucl. Eng. Des.,2016

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