Zobrazeno 1 - 10
of 15
pro vyhledávání: '"David Hambley"'
Publikováno v:
MRS Advances.
Electrochemical corrosion of lower-activity spent fuel simulants, SIMFUELs, has been investigated in support of on-going analogous studies of a real AGR spent nuclear fuel electrode. Two electrode coupling methods have been investigated, to study the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2b692626400e800d880414ec0203f43c
https://doi.org/10.1557/s43580-022-00349-5
https://doi.org/10.1557/s43580-022-00349-5
Publikováno v:
Siberry, A, Hambley, D, Adamska, A M & Springell, R S 2021, ' A mathematical model to describe the alpha dose rate from a UO2 surface ', Radiation Physics and Chemistry, vol. 182, 109359 . https://doi.org/10.1016/j.radphyschem.2021.109359
A model to determine the dose rate of a planar alpha-emitting surface has been developed. The approach presented is a computationally efficient mathematical model using stopping range data from the Stopping Ranges of Ions in Matter (SRIM) software. T
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f54544597db54a07e394f88411215b93
https://research-information.bris.ac.uk/en/publications/25f40a25-0294-4376-9925-670a34940dee
https://research-information.bris.ac.uk/en/publications/25f40a25-0294-4376-9925-670a34940dee
The behavior of advanced gas reactor simulated spent nuclear fuels in wet interim storage conditions
Publikováno v:
Progress in Nuclear Science and Technology. 5:140-143
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::56e6bfaac44f124a7787329ad1425d82
https://doi.org/10.15669/pnst.5.140
https://doi.org/10.15669/pnst.5.140
Autor:
Elizabeth A. Howett, David Hambley, Nadya Rauff-Nisthar, Colin Boxall, Richard J. Wilbraham, Zoltan Hiezl, Cristiano Padovani, William E. Lee
Publikováno v:
Progress in Nuclear Science and Technology. 5:213-216
Analysis of advanced gas-cooled reactor (AGR) simulated used nuclear fuels (SIMFuels) has been carried out using micro-Raman spectroscopy in order to understand the effect lanthanide species (e.g. Nd, Y, Ce), representative of fission products genera
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e53556b478da5492a3736609c4f9a58a
https://doi.org/10.15669/pnst.5.213
https://doi.org/10.15669/pnst.5.213
Publikováno v:
Siberry, A, Hambley, D, Adamska, A M & Springell, R 2021, ' A geometrical model to describe the alpha dose rates from particulates of UO2 in water ', Radiation Physics and Chemistry, vol. 188, 109677 . https://doi.org/10.1016/j.radphyschem.2021.109677
A model investigating the role of geometry on the alpha dose rate of spent nuclear fuel has been developed. This novel approach utilises a new piecewise function to describe the probability of alpha escape as a function of particulate radius, decay r
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f8453ac8fecca5312987df0e785de59c
https://doi.org/10.1016/j.radphyschem.2021.109677
https://doi.org/10.1016/j.radphyschem.2021.109677
Publikováno v:
Journal of Nuclear Materials. 498:187-198
A small proportion of irradiated Advanced Gas-cooled Reactor (AGR) fuel cladding can be susceptible to intergranular stress corrosion cracking (IGSCC) when stored in pond water containing low chloride concentrations, but corrosion is known to be prev
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a16405a527f18e0a4bf851e9db4963b0
https://doi.org/10.1016/j.jnucmat.2017.10.017
https://doi.org/10.1016/j.jnucmat.2017.10.017
Publikováno v:
Journal of Nuclear Materials. 552:152986
A number of cans of spent nuclear fuel from the UK's Windscale advanced gas-cooled reactor have been recovered from over four decades of pond storage to be repackaged. All the cans were found to be flooded and those with cut sections of pins containe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::48067749e13705261c16f59ee2d15f00
https://doi.org/10.1016/j.jnucmat.2021.152986
https://doi.org/10.1016/j.jnucmat.2021.152986
When spent nuclear fuel is being dried ahead of either interim storage or long term disposal it is necessary to be able to confirm that the required level of dryness has been achieved. This has typically involved a vacuum rebound test however this me
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::867739dee194be857eb6997a495d2ca7
A drying rig has been constructed to allow detailed comparison of both vacuum drying and flowed gas drying of spent nuclear fuels in response to the upcoming closure of the Thorp reprocessing facility at Sellafield, UK. Drying will be needed ahead of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f792e7acf297ce67804594ea3e89db87
Publikováno v:
MRS Advances. 2:615-620
The corrosion of unirradiated and unsensitized Advanced Gas-cooled Reactor cladding material, 20/25/Nb stainless steel, was studied as a function of temperature and [Cl−] typical of those found in interim spent fuel storage pond waters. With respec
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e12c72829c71efab94ebe6da7b5220aa
https://doi.org/10.1557/adv.2016.651
https://doi.org/10.1557/adv.2016.651