Zobrazeno 1 - 10
of 82
pro vyhledávání: '"Barry Marsden"'
Autor:
Bruce Davies, Neil Bourne, Paul Mummery, Christoph Rau, Mark S. Davies, J. Wade-zhu, A. Tzelepi, Barry Marsden, A.j. Bodey, Abbie Jones, Ram Krishna
Publikováno v:
Carbon. 168:230-244
Herein, the first study is presented using 4D synchrotron X-ray microtomography to capture all stages of crack development in neutron irradiated and radiolytically oxidised nuclear graphite. Employing a novel loading setup, specimens of Gilsocarbon g
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::54f839d505bc4c362700d0ff9dceb6e6
https://doi.org/10.1016/j.carbon.2020.06.051
https://doi.org/10.1016/j.carbon.2020.06.051
Publikováno v:
Surface and Interface Analysis. 53:90-99
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a36863af5e38b263fd4ec367ec5029bb
https://doi.org/10.1002/sia.6876
https://doi.org/10.1002/sia.6876
Autor:
Zhoutong He, Alex Theodosiou, Maoyuan Cai, Andy Smith, Abbie Jones, Barry Marsden, Hefei Huang, Xingtai Zhou
Publikováno v:
SSRN Electronic Journal.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b9cb54d9a7af93803dad84cfd25869cc
https://doi.org/10.2139/ssrn.4250837
https://doi.org/10.2139/ssrn.4250837
Autor:
Yongqi Zhu, Zhoutong He, Huilei Ma, Fanggang Liu, Alex Theodosiou, Andy Smith, Abbie Jones, Barry Marsden, Xingtai Zhou
Publikováno v:
Journal of Nuclear Materials. 559:153460
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2ee0dc46688bb43392913bd433997f40
https://doi.org/10.1016/j.jnucmat.2021.153460
https://doi.org/10.1016/j.jnucmat.2021.153460
Publikováno v:
Journal of Nuclear Materials. 557:153314
For the first time, the influence of pore closure on elastic modulus in the UK's Magnox and Advanced Gas Cooled Reactors (AGRs) graphite was determined by subjecting the graphite samples to high hydrostatic pressure and dynamic loading. Two grades of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b0bf45a169e186113b7b87438761f314
https://doi.org/10.1016/j.jnucmat.2021.153314
https://doi.org/10.1016/j.jnucmat.2021.153314
Autor:
Nicholas Warren, Barry Marsden, Graham Hall, Timothy Yates, Paul Mummery, Muhammad Fahad, Kevin McNally
Publikováno v:
Nuclear Engineering and Design. 324:390-401
The structural integrity of nuclear graphite bricks is important in Advanced Gas-cooled Reactors (AGRs) as they not only provide moderation but channels for fuel, cooling and control rods. AGR graphite moderator bricks are subjected to fast neutron i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::01e85780956a7747066f157d7bcac687
https://doi.org/10.1016/j.nucengdes.2017.09.014
https://doi.org/10.1016/j.nucengdes.2017.09.014
Autor:
Douglas L. Abernathy, Anne A. Campbell, Barry Marsden, Jiao Y. Y. Lin, Matthew B. Stone, Yongqiang Cheng, Fahima Islam, Abdallah Qteish, Iyad Al-Qasir, Gabriele Sala, Kemal Ramić
Publikováno v:
Annals of Nuclear Energy. 161:108437
Graphite has been of great interest since the dawn of the nuclear era. In this work, we will focus on the thermal neutron scattering of two types of nuclear graphite that have different microstructures, namely, the historic PGA which has a very aniso
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::28ed256ca0aa29fa901869a95ec426b1
https://doi.org/10.1016/j.anucene.2021.108437
https://doi.org/10.1016/j.anucene.2021.108437
Publikováno v:
McNally, K, Warren, N, Fahad, M, Hall, G & Marsden, B J 2017, ' A core-monitoring based methodology for predictions of graphite weight loss in AGR moderator bricks ', Nuclear Engineering and Design, vol. 314, pp. 56-66 . https://doi.org/10.1016/j.nucengdes.2016.12.032
Physically based models, resolved using the finite element (FE) method are often used to model changes in dimensions and the associated stress fields of graphite moderator bricks within a reactor. These models require inputs that describe the loading
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d42d90816e4d6589cf0503c7a76d9e18
https://doi.org/10.1016/j.nucengdes.2016.12.032
https://doi.org/10.1016/j.nucengdes.2016.12.032
Publikováno v:
McNally, K, Fahad, M, Tan, E, Warren, N, Hall, G N & Marsden, B J 2016, ' A numerical study of internal brick stresses in AGR moderator bricks ', Nuclear Engineering and Design, vol. 309, pp. 277-293 . https://doi.org/10.1016/j.nucengdes.2016.09.007
Physically-based models are often used to model changes in geometry and the associated stress fields of graphite moderator bricks within an advanced gas-cooled reactor (AGR). These models require inputs that describe the loading conditions, and coded
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7acbedb9b25c3a65971245ab47b2cf30
https://doi.org/10.1016/j.nucengdes.2016.09.007
https://doi.org/10.1016/j.nucengdes.2016.09.007
Publikováno v:
Annals of Nuclear Energy. 94:241-250
There is a significant amount of historic graphite data used in the safety cases for operating reactors and in research aimed at informing the designs of Generation IV High Temperature Gas-cooled Reactors (HTRs) and Molten Salt Reactors (MSR). Over t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4c641d57966aad63bd967272e91c1297
https://doi.org/10.1016/j.anucene.2016.03.019
https://doi.org/10.1016/j.anucene.2016.03.019