Grain Boundary Segregation of Substitutional Solutes/Impurities and Grain Boundary Decohesion in BCC Fe

Author:

He Xinfu,Wu Shi,Jia Lixia,Wang Dongjie,Dou Yankun,Yang Wen

Publisher

Elsevier BV

Reference13 articles.

1. IAEA Nuclear Energy Series. Integrity of Reactor Pressure Vessels in Nuclear Power Plants: Assessment of Irradiation Embrittlement Effects in Reactor Pressure Vessel Steels. No. NP-T-3.11 2009.

2. Microstructural characterization of RPV steels - series 3, report 1[R]. Joint EPRI-CRIEPI RPV Embrittlement studies (1999-2004). EPRI, Palo Alto, CA:2002, 1001015.

3. Structure and strength of <110> tilt grain boundaries in bcc Fe: An atomistic study;Terentyev;Computational Materials Science,2010

4. Dimensionality of interstitial He migration in h1 1 0i tilt grain boundaries in a-Fe;Terentyev;Computational Materials Science,2010

5. Interstitial helium diffusion mechanisms in h110i tit grain boundaries in BCC FeCr alloys: An atomistic study;He;Journal of Nuclear Materials,2013

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