Retention and surface blistering of helium irradiated tungsten as a first wall material-Reference-Cited by-同舟云学术

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Retention and surface blistering of helium irradiated tungsten as a first wall material

Published:2005-12 Issue:3 Volume:347 Page:289-297
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Gilliam S.B.,Gidcumb S.M.,Parikh N.R.,Forsythe D.G.,Patnaik B.K.,Hunn J.D.,Snead L.L.,Lamaze G.P.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference12 articles.

1. Chamber wall response to target implosion in inertial fusion reactors: new and critical assessments

2. Dynamic chamber armor behavior in IFE and MFE

3. New critical assessments of chamber and wall response to target implosion in inertial fusion reactors

4. Surface damage of 316 stainless steel irradiated with 4HE+ to high doses

5. The behaviour of surfaces under ion bombardment

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1. Sputtering fabrication of isolated W nanocolumns: A possible alternative as plasma facing material for nuclear fusion reactors;Nuclear Materials and Energy;2024-09

2. The distribution and segregation behaviors of helium in tungsten Σ5(310)/[001] grain boundary region: A first-principles study;Journal of Applied Physics;2024-03-01

3. Observation of Deeper Blister Skin Thickness Compared with the Stopping Range of High-Energy Helium in Tungsten for a Nuclear Fusion System;2024

4. Study of irradiation-induced vacancy-type defects in tungsten using positron annihilation spectroscopy;Nuclear Materials and Energy;2023-12

5. The effect of screw dislocation on Helium Bubble growth in Tungsten: molecular dynamic simulation study;Computational Materials Science;2023-10

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