Irradiation in BCC materials: Defect-induced changes of the effective dislocation mobility and their relation with the dose-dependent fracture response-Reference-Cited by-同舟云学术

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Irradiation in BCC materials: Defect-induced changes of the effective dislocation mobility and their relation with the dose-dependent fracture response

Published:2021-11 Issue: Volume:141 Page:103926
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Singh Kulbir,Robertson C.^ORCID,Bhaduri A.K.^ORCID

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference75 articles.

1. Irradiation effects in ferritic steels;Lechtenberg;J. Nucl. Mater.,1985

2. Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phénix;Dubuisson;J. Nucl. Mater.,1993

3. Ferritic/Martensitic steels for next-generation reactors;Klueh;J. Nucl. Mater.,2007

4. Structural Materials for Liquid Metal Cooled Fast Reactor Fuel Assemblies-Operational Behaviour;IAEA,2012

5. High temperature materials for nuclear fast fission and fusion reactors and advanced fossil power plants;Jayakumar;Procedia Eng.,2013

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. Irradiation dose and temperature effects on BCC material with dislocation based crystal plasticity;Annals of Nuclear Energy;2024-04

2. High-pressure phase transformations and lattice distortions in industrial AISI 1070 steel: Insights from Debye-Scherrer ring integration;Materials Science and Engineering: A;2024-04

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