Material transport parameters for irradiated nickel and austenitic Fe-Cr-Ni alloys
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference27 articles.
1. Recent insights on the swelling and creep of irradiated austenitic alloys
2. Radiation-induced segregation in binary and ternary alloys
3. Self-diffusion in austenitic Fe-Cr-Ni alloys
4. Direct measurement of small diffusion coefficients with secondary ion mass spectroscopy
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1. Theoretical prediction of radiation-enhanced diffusion behavior in nickel under self-ion irradiation;Nuclear Science and Techniques;2020-08
2. Displacement Damage in Irradiated Metals and Semiconductors;Solid State Physics - Advances in Research and Applications;1998
3. Annihilation of freely migrating defects by cascade remnants in Cu-1% Au alloys;Journal of Nuclear Materials;1996-11
4. Phase transformations under irradiation;Journal of Nuclear Materials;1994-10
5. Experimental studies of free defect generation during irradiation — Implications for reactor environments;Journal of Nuclear Materials;1993-10
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