A model to describe the anisotropic viscoplastic behaviour of Zircaloy-4 tubes-Reference-Cited by-同舟云学术

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A model to describe the anisotropic viscoplastic behaviour of Zircaloy-4 tubes

Published:1996-11 Issue:2-3 Volume:238 Page:135-162
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Delobelle P.,Robinet P.,Geyer P.,Bouffioux P.

Publisher

Elsevier BV

Subject

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

Reference38 articles.

1. Le Crayon Combustible des RéacteursàEau Pressurisée de Grande Puisance;Baron;Rapport EDF HT M2/88-27 A,1989

2. Creep of Zirconium Alloys in Nuclear Reactors;Franklin;ASTM Spec. Tech. Publ.,1986

3. Caractérisation des Tubes en Zircaloy 4;Bouffioux;Doc. Tech. EDF, No. DTI CB-03,1991

4. Analyse de Texture Cristallographique des Produits en Zircaloy 4;Bouffioux;Doc. Tech. EDF, No. DTI CB-04,1991

5. Réalisation d'une machine de fluage biaxiale (traction-torsion) à contraintes constantes

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1. Polycrystalline Simulations of In-Reactor Deformation of Zircaloy-4 Cladding Tubes during Nominal Operating Conditions;Zirconium in the Nuclear Industry: 20th International Symposium;2023-11-01

2. Implementation of ABAQUS User Subroutines for Viscoplasticity of 316 Stainless Steel and Zircaloy-4;Metals;2023-09-04

3. Polycrystalline modeling of the behavior of neutron-irradiated recrystallized zirconium alloys during strain path change tests;International Journal of Plasticity;2020-11

4. Radiation Effects in Zirconium Alloys;Comprehensive Nuclear Materials;2020

5. Measurement of directional anisotropy coefficients for AA7020-T6 tubes and prediction of forming limit curve;The International Journal of Advanced Manufacturing Technology;2018-02-04

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