Behavior of zirconium fuel cladding under fast pressurization rates-Reference-Cited by-同舟云学术

Behavior of zirconium fuel cladding under fast pressurization rates

Published:2008-06 Issue:6 Volume:238 Page:1441-1447
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Kim Jun Hwan,Lee Myoung Ho,Jeong Yong Hwan,Lim Jae Gwan

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.

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3. Modified ring stretch tensile testing of Zr–1Nb cladding;Cohen,1997

4. NSRR/RIA experiments with high-burnup PWR fuels;Fuketa;Nucl. Safety,1996

5. Out-of-pile and in-pile performance of advanced zirconium alloys (HANA) for high-burnup fuel;Jeong;J. Nucl. Sci. Technol.,2006

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