Zobrazeno 1 - 10
of 71
pro vyhledávání: '"Mark R. Wenman"'
The precipitation of hydrides in zirconium alloys is accompanied by a significant and anisotropic volumetric expansion. Previous literature quantified the misfit both theoretically and experimentally, but these values differ greatly; the experimental
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::28d2701df210929d20c6106d3bd716b3
http://hdl.handle.net/10044/1/97939
http://hdl.handle.net/10044/1/97939
Autor:
Jiatu Liu, Claudia Gasparrini, Joshua T. White, Kyle Johnson, Denise Adorno Lopes, Vanessa K. Peterson, Andrew Studer, Grant J. Griffiths, Gregory R. Lumpkin, Mark R. Wenman, Patrick A. Burr, Elizabeth S. Sooby, Edward G. Obbard
Publikováno v:
Journal of Nuclear Materials. 575:154215
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d76ff2ea24467ca8c2376328da5860cf
https://doi.org/10.1016/j.jnucmat.2022.154215
https://doi.org/10.1016/j.jnucmat.2022.154215
Publikováno v:
Journal of Nuclear Materials. :154391
Tens of Zr inter-atomic potentials (force fields) have been developed to enable atomic-scale simulations of Zr alloys. These can provide critical insight in the in-reactor behaviour of nuclear fuel cladding and structural components exposed, but the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::efe98cd4c2a2f42f975df90ff995aba5
https://doi.org/10.1016/j.jnucmat.2023.154391
https://doi.org/10.1016/j.jnucmat.2023.154391
Publikováno v:
MRS Advances. 5:559-567
Crack initiation in zirconium alloys is an important issue for the safety of water-cooled fission reactors. Zirconium hydrides that precipitate in service are potential crack nucleation sites. In this work, the deformation and cracking of zirconium h
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d0df890b4219759247ca89a9f57bdaea
https://doi.org/10.1557/adv.2020.145
https://doi.org/10.1557/adv.2020.145
Publikováno v:
Procedia Structural Integrity. 28:1520-1535
SiC continuous fibre reinforced SiC matrix (SiC-SiC) composites are a proposed material for accident tolerant fuel cladding. Thermomechanical models of SiC-based cladding under light water conditions indicate that microcracking in the radial directio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1f276470977e5bd9151576be7206f653
https://doi.org/10.1016/j.prostr.2020.10.125
https://doi.org/10.1016/j.prostr.2020.10.125
Publikováno v:
Procedia Structural Integrity. 28:1856-1874
Peridynamics is a continuum mechanics modelling method, which offers advantages over traditional continuum methods when modelling brittle fracture. Brittle fracture typically follows a Weibull fracture distribution, but this behaviour is not well rep
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e0cba3c7a8ca7e15e72f0c19ee6674c5
https://doi.org/10.1016/j.prostr.2020.11.009
https://doi.org/10.1016/j.prostr.2020.11.009
Autor:
Claudia Gasparrini, James O. Douglas, Christopher D. Hardie, Lyndon Edwards, Nick Riddle, Paul A. J. Bagot, Mark R. Wenman, Megan Carter, Michael P. Moody
The neutron irradiation response of a novel hot isostatically pressed SA508 Grade3 steel was studied, such to deduce any influence this unconventional RPV microstructure has on radiation response. In particular, the role of elevated ferrite fraction
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2e8ee8a9922ae6209ec8b11860e6171e
https://ora.ox.ac.uk/objects/uuid:19bcab22-7648-4a69-bc93-77422799a780
https://ora.ox.ac.uk/objects/uuid:19bcab22-7648-4a69-bc93-77422799a780
Publikováno v:
Journal of Nuclear Materials. 572:154091
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::808090429f4742bfc706a6fb6a210d9b
https://doi.org/10.1016/j.jnucmat.2022.154091
https://doi.org/10.1016/j.jnucmat.2022.154091
Hydride formation in zircaloy-4 under cyclic thermomechanical loading has been investigated using characterized notched beam samples in four-point beam testing, and microstructurally-representative crystal plasticity modelling of the beam tests which
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::005cda34f5be7e87e1520f9ee262f2d1
http://hdl.handle.net/10044/1/93788
http://hdl.handle.net/10044/1/93788
There is clear evidence in the literature that iron segregates to the interface of second phase particles (SPPs) in unirradiated Zr-Nb alloys, and that it does not do so in the presence of radiation damage. In this work, a discrete dislocation plasti
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e618ecd3a7469e627b5b407fa9454682
http://hdl.handle.net/10044/1/90434
http://hdl.handle.net/10044/1/90434