Deuterium retention in tungsten and reduced activation steels after 3 MeV proton irradiation-Reference-Cited by-同舟云学术

Deuterium retention in tungsten and reduced activation steels after 3 MeV proton irradiation

Published:2020-05 Issue: Volume:23 Page:100742
ISSN:2352-1791
Container-title:Nuclear Materials and Energy
language:en
Short-container-title:Nuclear Materials and Energy

Author:

Möller S.^ORCID,Krug R.^ORCID,Rayaprolu R.,Kuhn B.^ORCID,Joußen E.,Kreter A.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics

Reference17 articles.

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2. Modelling deuterium release during thermal desorption of D+-irradiated tungsten;Poon;J. Nucl. Mater.,2008

3. Structural defect accumulation in tungsten and tungsten-5wt.% tantalum under incremental proton damage;Ipatova;J. Nucl. Mater.,2018

4. Saturation of deuterium retention in self-damaged tungsten exposed to high-flux plasmas;Hoen;Nucl. Fusion,2012

5. Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part II: steels pre-damaged with 20 MeV W ions and high heat flux;Ogorodnikova;Nucl. Fusion,2017

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2. A critical review of experiments on deuterium retention in displacement-damaged tungsten as function of damaging dose;Materials Research Express;2023-10-01

3. Microstructure of a heavily irradiated metal exposed to a spectrum of atomic recoils;Scientific Reports;2023-01-30

4. Dynamic equilibrium of displacement damage defects in heavy-ion irradiated tungsten;Acta Materialia;2023-01

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