Delayed-hydride cracking (DHC) of cladding materials: An analysis for storage and disposal of spent nuclear fuel-Reference-Cited by-同舟云学术

Delayed-hydride cracking (DHC) of cladding materials: An analysis for storage and disposal of spent nuclear fuel

Published:2019-08 Issue: Volume:350 Page:128-136
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Ahn Tae M.

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

Reference48 articles.

1. Nucleation Kinetics of Crystalline Ordering in Alloy 600 at Elevated Temperature;Ahn,2018

2. An approach to model abstraction of stress corrosion cracking damage in management of spent nuclear fuel and high level waste;Ahn,2013

3. Dissolution Kinetics of Commercial Spent Nuclear Fuels in the Potential Yucca Mountain Repository Environment;Ahn,2008

4. Dry Oxidation and Fracture of LWR SPENT-FUels. NUREG-1565;Ahn,1996

5. Potential stress on cladding imposed by the matrix swelling from alpha decay in high burnup spent nuclear fuel;Ahn,2013

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