Hydrogen diffusion in zirconium cladding alloys with an inner liner as quantified by neutron radiography and nanoindentation-Reference-Cited by-同舟云学术

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Hydrogen diffusion in zirconium cladding alloys with an inner liner as quantified by neutron radiography and nanoindentation

Published:2023-10 Issue: Volume:584 Page:154574
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Fagnoni Francesco,Trtik Pavel,Wheeler Jeffrey M.,Zubler Robert,Bertsch Johannes,Duarte Liliana I.

Publisher

Elsevier BV

Subject

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

Reference40 articles.

1. Zirconium alloys in nuclear technology;Krishnan;Proc. Indian Acad. Sci. (Eng. Sci.),1981

2. The development and applications of zirconium alloys;Northwood;Mater. Des.,1985

3. 2.07 - zirconium alloys: properties and characteristics;Lemaignan,2012

4. Pellet-clad interaction (PCI) failures of zirconium alloy fuel -a review;Cox;J. Nucl. Mater.,1990

5. H.S. Rosenbaum and J.S. Armijo, ‘Inner liner for fuel cladding having zirconium barriers layers’, EP0635845A1, Jan. 25, 1995 Accessed: Aug. 23, 2022. [Online]. Available: https://patents.google.com/patent/EP0635845A1/en.

Cited by 2 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Thermal creep in a pre-hydrided Zr1 % Nb nuclear fuel cladding tube;Journal of Nuclear Materials;2024-08

2. Effect of hydride orientation on tensile properties and crack formation in zirconium alloy cladding tubes;Journal of Nuclear Materials;2024-08

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