Development of a program for high-temperature design evaluation according to RCC-MRx-Reference-Cited by-同舟云学术

Development of a program for high-temperature design evaluation according to RCC-MRx

Published:2017-12 Issue: Volume:324 Page:181-195
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Lee Hyeong-Yeon,Won Min-Gu,Son Seok-Kwon^ORCID,Huh Nam-Su

Funder

NRF

KAERI

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference14 articles.

1. Status of Fast Reactor Research and Technology Development, IAEA-TECDOC-1691;Abram,2012

2. ASME Boiler and Pressure Vessel Code, 2015a, Section III, Rules for Construction of Nuclear Power Plant Components, Division 1, Subsection NH, Class 1 Components in Elevated Temperature Service, ASME.

3. ASME Boiler and Pressure Vessel Code, 2015b, Section III, Rules for Construction of Nuclear Power Plant Components, Division 1, Subsection NB, Class 1 Components, ASME.

4. ASME Boiler and Pressure Vessel Code, 2017, Section III, Rules for Construction of Nuclear Power Plant Components, Division 5, High temperature reactors, ASME.

5. Comparison of elevated temperature design codes of ASME Subsection NH and RCC-MRx;Lee;Nucl. Eng. Des.,2016

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