Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Steven Knol"'
Autor:
Alexander J. Leide, Thomas A. Haynes, Nassia Tzelepi, John Payne, Matthew Jordan, Steven Knol, Jan A. Vreeling, Mark Davies, David T. Goddard, Manuel J. Pfeifenberger, Markus Alfreider, Daniel Kiener, Dong Liu
Publikováno v:
Nuclear Materials and Energy, Vol 36, Iss , Pp 101470- (2023)
Coated fuel particles, most commonly tri-structural isotropic (TRISO), are intended for application in several designs of advanced nuclear reactors. A complete understanding of the residual stresses and local properties of these particles through the
Externí odkaz:
https://doaj.org/article/e49510a953184b4b8532015d566ce92c
Autor:
Dong Liu, Steven Knol, Jon Ell, Harold Barnard, Mark Davies, Jan A. Vreeling, Robert O. Ritchie
Publikováno v:
Materials & Design, Vol 187, Iss , Pp - (2020)
Two types of dedicated Tristructural isotropic (TRISO) nuclear fuel particles, PyC-1 (Kernel/Buffer/PyC) and PyC-2 (Kernel/Buffer/SiC/PyC) from PYCASSO (Pyrocarbon irradiation for creep and swelling/shrinkage of objects) neutron irradiation experimen
Externí odkaz:
https://doaj.org/article/53b0f6ac92514dfb9437eed3a8e66549
Autor:
Harold Barnard, Jon Ell, Robert O. Ritchie, Jan A. Vreeling, Dong Liu, Steven Knol, Mark Davies
Publikováno v:
Materials & Design, Vol 187, Iss, Pp-(2020)
Liu, L, Knol, S, Ell, J, S. Barnard, H, Davies, M, Vreeling, J & Robert O., R 2020, ' X-ray tomography study on the crushing strength and irradiation behaviour of dedicated tristructural isotropic nuclear fuel particles at 1000°C ', Materials and Design, vol. 187, 108382 . https://doi.org/10.1016/j.matdes.2019.108382
Liu, L, Knol, S, Ell, J, S. Barnard, H, Davies, M, Vreeling, J & Robert O., R 2020, ' X-ray tomography study on the crushing strength and irradiation behaviour of dedicated tristructural isotropic nuclear fuel particles at 1000°C ', Materials and Design, vol. 187, 108382 . https://doi.org/10.1016/j.matdes.2019.108382
Two types of dedicated Tristructural isotropic (TRISO) nuclear fuel particles, PyC-1 (Kernel/Buffer/PyC) and PyC-2 (Kernel/Buffer/SiC/PyC) from PYCASSO (Pyrocarbon irradiation for creep and swelling/shrinkage of objects) neutron irradiation experimen
Autor:
Ian P. Shapiro, Nadia Rohbeck, Steven Knol, Bing Liu, Ping Xiao, Jean-Michel Escleine, Marc Perez, Dimitrios Tsivoulas
Publikováno v:
Journal of Materials Science
Rohbeck, N 2017, ' Comparison study of silicon carbide coatings produced at different deposition conditions with use of high temperature nanoindentation ', Journal of Materials Science, vol. 52, no. 4, pp. 1868-1882 . https://doi.org/10.1007/s10853-016-0476-5
Rohbeck, N 2017, ' Comparison study of silicon carbide coatings produced at different deposition conditions with use of high temperature nanoindentation ', Journal of Materials Science, vol. 52, no. 4, pp. 1868-1882 . https://doi.org/10.1007/s10853-016-0476-5
The elastic modulus and hardness of different silicon carbide (SiC) coatings in tristructural-isotropic (TRISO) fuel particles were measured by in situ high temperature nanoindentation up to 500 °C. Three samples fabricated by different research ins
Autor:
Jean-Michel Escleine, Marc Perez, Ping Xiao, Ian P. Shapiro, Nadia Rohbeck, Dimitrios Tsivoulas, Steven Knol
Publikováno v:
Rohbeck, N, Tsivoulas, D, Shapiro, I P, Xiao, P, Knol, S, Escleine, J-M & Perez, M 2015, ' In-situ nanoindentation of irradiated silicon carbide in TRISO particle fuel up to 500°C ', Journal of Nuclear Materials, vol. 465, pp. 692-694 . https://doi.org/10.1016/j.jnucmat.2015.06.035
The evolution of hardness and elastic modulus with temperature for silicon carbide (SiC) coatings in tristructural-isotropic fuel was measured by in-situ nanoindentation from ambient temperature up to 500 °C. Over this temperature range a significan
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e5f152e28f08a6c8bad6e1d55dd5708b
http://www.manchester.ac.uk/escholar/uk-ac-man-scw:275761
http://www.manchester.ac.uk/escholar/uk-ac-man-scw:275761
Publikováno v:
Journal of Nuclear Materials. :820-834
Americium is a strong contributor to the long term radiotoxicity of high activity nuclear waste. Transmutation by irradiation in nuclear reactors or Accelerator Driven System (ADS, subcritical reactors dedicated to transmutation) of long-lived nuclid