Hydride reorientation and its impact on ambient temperature mechanical properties of high burn-up irradiated and unirradiated recrystallized Zircaloy-2 nuclear fuel cladding with an inner liner-Reference-Cited by-同舟云学术

Hydride reorientation and its impact on ambient temperature mechanical properties of high burn-up irradiated and unirradiated recrystallized Zircaloy-2 nuclear fuel cladding with an inner liner

Published:2017-10 Issue: Volume:494 Page:114-126
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Auzoux Q.,Bouffioux P.,Machiels A.,Yagnik S.,Bourdiliau B.,Mallet C.,Mozzani N.^ORCID,Colas K.

Funder

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

Electricité de France

Electric Power Research Institute

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference54 articles.

1. Cladding Considerations for the Transportation and Storage of Spent Fuel,2003

2. The Annual Report on Irradiation Tests of High Burnup Fuels in Fy 2001, in: Integrated Evaluation on Irradiation Behavior of BWR High Burnup Fuel, March 2002 (in Japanese).

3. Control of hydride orientation in zircaloy

4. The stress orientation of hydride in zirconium alloys

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