Zobrazeno 1 - 10
of 25
pro vyhledávání: '"Samuel A. Humphry-Baker"'
Autor:
Neal Parkes, Russel Dodds, Andy Watson, David Dye, Chris Hardie, Samuel A. Humphry-Baker, Alexander J. Knowles
Tungsten is considered as a primary material for the divertor and first wall in many fusion reactor designs. There has been further interest in nano-structured multi-phase tungsten alloys and composites, such as oxide dispersion strengthened alloys,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::05f68de93da11dc5a68b76ba478d5fca
http://hdl.handle.net/10044/1/104091
http://hdl.handle.net/10044/1/104091
Autor:
Colin G. Windsor, Jack O. Astbury, J. Guy Morgan, Christopher L. Wilson, Samuel A. Humphry-Baker
The FISPACT-II code is used to compute the levels of activation and transmutation of tungsten borides for shielding the central high temperature superconductor core of a spherical tokamak fusion power plant during operations at 200 MW fusion power fo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7eafd3b007d3425dff4eef773fae0de5
http://hdl.handle.net/10044/1/94068
http://hdl.handle.net/10044/1/94068
Publikováno v:
Journal of Nuclear Materials. 524:239-246
Tungsten carbide (WC) has been found to have higher resistance to plasma-induced thermal-shock compared to rolled tungsten. The electron beam device JUDITH 1 was used to simulate likely thermal shock conditions induced by edge localised modes and pla
Publikováno v:
Journal of Nuclear Materials. 565:153762
The growth mechanism of large WC crystals from a liquid Co-based flux is identified. This is achieved by systematically varying the growth temperature and Co content from 1200 to 1400 °C and 70–83 at.% respectively. Crystal growth was characterise
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::1701bb2f1c334b94db5633865c67bf81
http://hdl.handle.net/10044/1/89823
http://hdl.handle.net/10044/1/89823
Iron is a candidate to replace cobalt in WC hardmetals, due to its lower cost and toxicity. A WC-FeCr hardmetal was compression tested at 900-1200 {\deg}C. Particular attention is paid to the steady-state creep rates and stress-exponents (n) during i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::fe3cfe43c7ecbc22427c09240cd90743
http://arxiv.org/abs/2008.13565
http://arxiv.org/abs/2008.13565
A cobalt-free tungsten carbide cermet (WC-FeNi) has been subjected to oxyacetylene flame tests to simulate extreme operating conditions such as a worst-case fusion reactor accident. In such an accident, air-ingress to the reactor may impinge on compo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::99b29a2301f036b0a05ac3bf437c87e8
http://hdl.handle.net/10044/1/81982
http://hdl.handle.net/10044/1/81982
Autor:
Dóra Nagy, Samuel A. Humphry-Baker
Publikováno v:
Scripta Materialia. 209:114373
A tungsten oxidation mechanism map is developed to clarify literature confusion about the dominant oxidation kinetic regime and to enable improved predictions in extreme environments. Thermogravimetry data is systematically extracted from 14 papers i
Autor:
George Davey Smith, Samuel A. Humphry-Baker, Robert W. Harrison, Alexander J. Knowles, William E. Lee, Graeme Greaves, Stephen E. Donnelly
Publikováno v:
Humphry-Baker, S A, Harrison, R W, Greaves, G, Knowles, A J, Smith, G D W, Donnelly, S E & Lee, W E 2018, ' A candidate fusion engineering material, WC-FeCr ', Scripta Materialia, vol. 155, pp. 129-133 . https://doi.org/10.1016/j.scriptamat.2018.06.027
A new candidate fusion engineering material, WC-FeCr, has been irradiated with He ions at 25 and 500 °C. Ions were injected at 6 keV to a dose of ~15 dpa and 50 at. % He, simulating direct helium injection from the plasma. The microstructural evolut
Autor:
James J. Davidson, Colin G. Windsor, Samuel A. Humphry-Baker, Charles J. R. McFadzean, J. Guy Morgan, Christopher L. Wilson, Jack O. Astbury
Publikováno v:
Nuclear Fusion. 61:086018
The favourable properties of tungsten borides for shielding the central high temperature superconductor (HTS) core of a spherical tokamak fusion power plant are modelled using the MCNP code. The objectives are to minimize the power deposition into th