Azimuthally anisotropic hydride lens structures in Zircaloy 4 nuclear fuel cladding: High-resolution neutron radiography imaging and BISON finite element analysis-Reference-Cited by-同舟云学术

Azimuthally anisotropic hydride lens structures in Zircaloy 4 nuclear fuel cladding: High-resolution neutron radiography imaging and BISON finite element analysis

Published:2017-12 Issue: Volume:496 Page:129-139
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Lin Jun-Li^ORCID,Zhong Weicheng,Bilheux Hassina Z.,Heuser Brent J.

Funder

U.S. Department of Energy

US Department of Energy Nuclear Energy Fuel Aging in Storage and Transportation IRP

US Department of Energy Accident Tolerant Fuel IRP

University of Illinois Campus Research Board

Scientific User Facilities Division, the Office of Basic Energy Sciences, U.S. Department of Energy

Publisher

Elsevier BV

Subject

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

Reference45 articles.

1. Corrosion of zirconium alloys used for nuclear fuel cladding;Motta;Annu. Rev. Mater. Res.,2015

2. FRAPCON-3: a Computer Code for the Calculation of Steady-state, Thermal-mechanical Behavior of Oxide Fuel Rods for High Burnup (No. NUREG/CR—6534-vol. 2; PNNL—11513-vol. 2);Berna,1997

3. Overview of EPRI fuel performance code FALCON;Yagnik;Therm. Perform. High Burn-Up LWR Fuel,1998

4. An object-oriented finite element framework for multiphysics phase field simulations;Tonks;Comput. Mater. Sci.,2012

5. Multidimensional multiphysics simulation of nuclear fuel behavior;Williamson;J. Nucl. Mater.,2012

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