[HTML][HTML] Fast release from clad and declad spent UOX PWR fuel segments in a bicarbonate solution under anoxic conditions
T Mennecart, C Cachoir, K Lemmens - Journal of Nuclear Materials, 2021 - Elsevier
For the safety assessment of Spent Nuclear Fuel (SNF) in disposal conditions, it is crucial to
determine the fast release of the potentially critical radionuclides (eg 129 I, 137 Cs, 99 Tc, 93 …
determine the fast release of the potentially critical radionuclides (eg 129 I, 137 Cs, 99 Tc, 93 …
[图书][B] A non-destructive method to determine the neutron production rate of a sample of spent nuclear fuel under standard controlled area conditions
P Schillebeeckx, M Verwerft, G Žerovnik, Y Parthoens… - 2020 - ejp-eurad.eu
A method to determine the neutron production rate of a sample of spent nuclear fuel by
means of nondestructive analysis conducted under controlled-area conditions is described …
means of nondestructive analysis conducted under controlled-area conditions is described …
Caesium and iodine release from spent mixed oxide fuels under repository relevant conditions: Initial leaching results
C Schreinemachers, G Leinders, T Mennecart… - MRS advances, 2022 - Springer
Autoclave leaching experiments are conducted on three well-characterised, irradiated, and
cladded mixed oxide fuel-rod segments with burnups ranging from 29 GWd/tHM to 52 …
cladded mixed oxide fuel-rod segments with burnups ranging from 29 GWd/tHM to 52 …
An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation
P Schillebeeckx, M Verwerft, P Romojaro… - Frontiers in Energy …, 2023 - frontiersin.org
A method to determine the neutron production rate of a spent nuclear fuel segment sample
by means of non-destructive assay conducted under standard controlled-area conditions is …
by means of non-destructive assay conducted under standard controlled-area conditions is …
[PDF][PDF] Leaching experiments on UOX and MOX spent fuel: Results and prospects of the SF-ALE project at SCK CEN
G Leinders, M Verwerft, J Eysermans… - Proceedings of …, 2021 - academia.edu
In the context of interim or long-term storage of spent nuclear fuel, as well as in final disposal
scenarios it is crucial to understand and accurately predict the materials' behavior …
scenarios it is crucial to understand and accurately predict the materials' behavior …
Characterisation of high burnup spent mixed oxide fuel after leaching at hyperalkaline pH in a reducing environment
C Schreinemachers, G Leinders, J Van Eyken… - MRS Advances, 2024 - Springer
Microstructural investigations of a Zircaloy-4 clad mixed oxide fuel rod segment with a
burnup of 50.3 GWd/tHM after exposure to a synthetic young cementitious water at a …
burnup of 50.3 GWd/tHM after exposure to a synthetic young cementitious water at a …
Sorptive interactions of selenium oxyanions with ferric oxyhydroxides
M Matulova - 2021 - inis.iaea.org
ABSTRACT MICHAELA MATULOVÁ: Sorptive interactions of selenium oxyanions with ferric
oxyhydroxides.[Dissertation thesis] Comenius University in Bratislava, Faculty of Natural …
oxyhydroxides.[Dissertation thesis] Comenius University in Bratislava, Faculty of Natural …