Retention properties in displacement damaged ultra-fine grain tungsten exposed to divertor plasma
One of the main advantages of using tungsten (W) as a plasma facing material (PFM) is its low uptake and retention of tritium. However, in high purity (ITER grade) W, hydrogenic retention increases significantly with neutron-induced displacement damage in the W lattice. This experiment examines an a...
Main Authors: | , , , , , , , , , , |
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Format: | Article |
Language: | English |
Published: |
Elsevier
2019-08-01
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Series: | Nuclear Materials and Energy |
Online Access: | http://www.sciencedirect.com/science/article/pii/S2352179118301704 |