Tritium Desorption Behavior and Microstructure Evolution of Beryllium Irradiated at Low Temperature Up to High Neutron Dose in BR2 Reactor
Author:
Affiliation:
1. Karlsruhe Institute of Technology, Institute for Applied Materials, Hermann-von-Helmholtz-Plarz 1, 76344 Eggenstein-Leopoldshafen, Germany
2. Institute of Nuclear Materials Science, SCK CEN, 2400 Mol, Belgium
Abstract
Publisher
MDPI AG
Subject
General Medicine
Link
https://www.mdpi.com/2673-4362/4/3/36/pdf
Reference34 articles.
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3. TEM investigation of long-term annealed highly irradiated beryllium;Leenaers;J. Nucl. Mater.,2008
4. Experimental determination of creep properties of beryllium irradiated to relevant fusion power reactor doses;Scibetta;J. Nucl. Mater.,2007
5. The SSC RIAR high-flux research reactors: Experience and possibilities of testing materials and mock-ups for fusion;Melder;Fus. Eng. Des.,2003
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1. Correction: Chakin et al. Tritium Desorption Behavior and Microstructure Evolution of Beryllium Irradiated at Low Temperature Up to High Neutron Dose in BR2 Reactor. J. Nucl. Eng. 2023, 4, 552–564;Journal of Nuclear Engineering;2024-03-08
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