The effect of hydride morphology on the failure strain of stress-relieved Zircaloy-4 cladding with an outer surface pre-crack under biaxial stress states-Reference-Cited by-同舟云学术

The effect of hydride morphology on the failure strain of stress-relieved Zircaloy-4 cladding with an outer surface pre-crack under biaxial stress states

Published:2019-03-22 Issue:5 Volume:56 Page:432-439
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Li Feng¹,Mihara Takeshi¹,Udagawa Yutaka¹^ORCID,Amaya Masaki¹

Affiliation:

1. Nuclear Safety Research Center, Japan Atomic Energy Agency, Tokai-mura, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2019.1592723

Reference20 articles.

1. U.S. AEC. Regulatory Guide 1.77 - Assumptions used for evaluating a control rod ejection accident for pressurized water reactors. U.S. Atomic Energy Commission - Directorate of Regulatory standards, Regulatory guide 1.77, 1974 May. Washington (DC).

2. NEA. Nuclear fuel behaviour under reactivity-initiated accident (RIA) conditions. France: Nuclear Energy Agency, OECD; 2010. (Report NEA No. 6847). ISBN 978-92-64-99113-2.

3. The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident (RIA)

4. Behavior of High-Burnup PWR Fuels with Low-Tin Zircaloy-4 Cladding under Reactivity-Initiated-Accident Conditions

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