Session: CS-12-01 High Temperature Codes and Standards

Paper Number: 106584

106584 - Development of a Web-Based Design Evaluation Platform for Elevated Temperature Design as per Asme Section Iii Division 5, Asme Cc-2843 and Rcc-Mrx 

An integrated web-based design evaluation platform of HITEP (HIgh Temperature design Evaluation Program) covering the three elevated temperature design rules of ASME BPVC Section III Division 5 Subsection HB (hereafter ‘ASME-HB’), ASME Code Case 2843-2(hereafter ‘CC-2843’) and RCC-MRx , in addition to light water reactor design rules of ASME BPVC Section III Subsection NB (hereafter ‘ASME-NB’) has been developed. CC-2843 is recently published code case of ASME Section VIII Division 2 based on the ASME-HB procedures with explicit consideration of creep. The evaluation module of ASME-NB has been added because the low-temperature design evaluations should be also conducted for a high-temperature component subjected to temperature fluctuations over the temperatures within and below the creep range where low-temperature evaluations should be conducted as per ASME-NB. The HITEP platform was intended to be used for reliable and efficient design evaluations of Generation IV nuclear reactor systems as well as of Generation III+ light water reactors. This platform of elevated temperature design parts can be used with high reliability and efficiency for the design of high temperature pressure boundary components or piping systems subjected to high-temperature operation at creep regime in a nuclear power plant, renewable or thermal power plants. It was shown that the platform can be reliably and efficiently used for the ETD of pressure boundary components and piping systems. The HITEP platform has been successfully used for the ETD of pressure boundary components and piping systems of the two large scale sodium test facilities of the STELLA-2 that is currently under operation and the thermal energy storage test facility of the TESET that is under construction at KAERI.

Presenting Author: Hyeong-Yeon LEE KAERI (Korea Atomic Energy Research Institute)

Presenting Author Biography: Dr. Hyeong-Yeon Lee is a principal researcher at KAERI. He has received Ph.D at KAIST in 1995 with a thesis on Fracture mechanics. Specialty is high-temperature design and defect assessment of pressure vessels and piping with more than 30 years of experience. He has produced 35 SCIE Journal papers as first (& corresponding) author, another 20 SCIE papers as corresponding author or co-author, and 28 domestic J papers.

Authors:

Hyeong-Yeon LEE KAERI (Korea Atomic Energy Research Institute)
Ki-Ean Nam KAERI (Korea Atomic Energy Research Institute)
Nam-Su Huh Seoul National University of Science and Technology
Min-Kyu Kim ThusTop Co., Ltd.