Search Results - "Leenaers, A."
-
1
Pore pressure estimation in irradiated UMo
Published in Journal of nuclear materials (01-11-2018)“…Image analysis was performed on SEM micrographs of recently irradiated UMo dispersion fuel plates. Detailed information on the fission gas inter-granular…”
Get full text
Journal Article -
2
High burn-up structure of U(Mo) dispersion fuel
Published in Journal of nuclear materials (01-08-2016)“…The evolution of the high burn-up structure (HBS) in U(Mo) fuel irradiated up to a burn-up of ∼70% 235U or ∼5 × 1021 f/cm3 or ∼120 GWd/tHM is described and…”
Get full text
Journal Article -
3
Transmission electron microscopy investigation of irradiated U–7 wt%Mo dispersion fuel
Published in Journal of nuclear materials (30-04-2008)“…The microstructural evolution of atomised U–7 wt%Mo alloy fuel under irradiation was investigated by transmission electron microscopy on material from the…”
Get full text
Journal Article -
4
Corrigendum to “Pore pressure estimation in irradiated UMo” [J. Nucl. Mater. 510 (2018) 472–483]
Published in Journal of nuclear materials (01-09-2020)Get full text
Journal Article -
5
Fuel swelling and interaction layer formation in the SELENIUM Si and ZrN coated U(Mo) dispersion fuel plates irradiated at high power in BR2
Published in Journal of nuclear materials (01-03-2015)“…In the framework of the SELENIUM project two full size flat fuel plates were produced with respectively Si and ZrN coated U(Mo) particles and irradiated in the…”
Get full text
Journal Article -
6
The initial formation stages of a nanobubble lattice in neutron irradiated U(Mo)
Published in Journal of nuclear materials (01-02-2020)“…Low burnup samples of U7wt%Mo with 10%, 15%, 20% and 25% 235U burnup were analysed by transmission electron microscopy in order to study the formation…”
Get full text
Journal Article -
7
Surface engineering of low enriched uranium–molybdenum
Published in Journal of nuclear materials (01-09-2013)“…Recent attempts to qualify the LEU(Mo) dispersion plate fuel with Si addition to the Al matrix up to high power and burn-up have not yet been successful due to…”
Get full text
Journal Article -
8
Aluminum cladding oxide growth prediction for high flux research reactors
Published in Journal of nuclear materials (01-02-2020)“…Aluminum cladding oxidation of research-reactor fuel elements at high power conditions has a disadvantageous effect on fuel performance due to the lower…”
Get full text
Journal Article -
9
U(Mo) grain refinement induced by irradiation with high energy iodine
Published in Journal of nuclear materials (01-05-2021)“…Grain refinement in U(Mo) has been achieved out-of-pile by irradiating an U(Mo) foil with 80 MeV high-flux 127I ions at 140°C up to a high dose of ~ 2.1 × 1018…”
Get full text
Journal Article -
10
Microstructure and calorimetric analysis of the UMn binary system
Published in Journal of nuclear materials (01-02-2019)“…The microstructure, growth kinetics, and the high temperature phase equilibria of the UMn binary system are investigated using differential scanning…”
Get full text
Journal Article -
11
A modelling study of the inter-diffusion layer formation in U-Mo/Al dispersion fuel plates at high power
Published in Journal of nuclear materials (01-02-2018)“…Post irradiation examinations of full-size U-Mo/Al dispersion fuel plates fabricated with ZrN- or Si- coated U-Mo particles revealed that the reaction rate of…”
Get full text
Journal Article -
12
STEM-EDS/EELS and APT characterization of ZrN coatings on UMo fuel kernels
Published in Journal of nuclear materials (01-12-2018)“…In the framework of the SELENIUM project, ZrN coated U-Mo fuel kernels were irradiated in the Belgium Reactor 2 of SCK•CEN to a plate average burnup of 48%…”
Get full text
Journal Article -
13
Microstructure of as atomized and annealed U-Mo7 particles: A SEM/EBSD study of grain growth
Published in Journal of nuclear materials (01-11-2017)“…Significant progresses in the performances under in-pile irradiation of particular U-Mo based fuels have been observed over the last fifteen years. One of the…”
Get full text
Journal Article -
14
Microstructural evolution of U(Mo)–Al(Si) dispersion fuel under irradiation – Destructive analyses of the LEONIDAS E-FUTURE plates
Published in Journal of nuclear materials (01-10-2013)“…Several irradiation experiments have confirmed the positive effect of adding Si to the matrix of an U(Mo) dispersion fuel plate on its in-pile irradiation…”
Get full text
Journal Article -
15
Swelling of U(Mo) dispersion fuel under irradiation – Non-destructive analyses of the SELENIUM plates
Published in Journal of nuclear materials (01-11-2013)“…Extensive fuel-matrix interactions leading to plate pillowing have caused a severe impediment on the development of a suitable high density low-enriched…”
Get full text
Journal Article -
16
Temperature Effects on Interdiffusion of Al and U-Mo under Irradiation
Published in Journal of nuclear materials (01-02-2021)“…A high-energy Xe ion irradiation experiment was conducted to investigate the temperature dependence of interdiffusion in bilayer Al-UMo samples under…”
Get full text
Journal Article -
17
Transmission electron microscopy investigation of neutron irradiated Si and ZrN coated UMo particles prepared using FIB
Published in Journal of nuclear materials (01-01-2018)“…Two fuel plates, containing Si and ZrN coated U-Mo fuel particles dispersed in an Al matrix, were irradiated in the BR2 reactor of SCK•CEN to a burn-up of ∼70%…”
Get full text
Journal Article -
18
Swelling of U(Mo)–Al(Si) dispersion fuel under irradiation – Non-destructive analyses of the LEONIDAS E-FUTURE plates
Published in Journal of nuclear materials (01-11-2012)“…In the framework of the elimination of High-Enriched Uranium (HEU) from the civil circuit, the search for an appropriate fuel to replace the high-enriched…”
Get full text
Journal Article -
19
3D reconstructions of irradiated U Mo fuel to understand breaching effects in ZrN diffusion barriers
Published in Journal of nuclear materials (01-11-2018)“…To understand interaction layer behavior in U-Mo fuel kernels coated with physical vapor deposition (PVD) ZrN barriers, two cubes of irradiated fuel were…”
Get full text
Journal Article -
20
Heavy ion irradiation of UMo/Al samples PVD coated with Si and ZrN layers
Published in Journal of nuclear materials (01-03-2013)“…Excessive U-Al interdiffusion hampers the development of UMo/Al based disperse fuel since several years. As a remedy, addition of diffusion limiting elements…”
Get full text
Journal Article