LWR severe accident simulation: synthesis of the results and interpretation of the first Phebus FP experiment FPT0

B Clément, N Hanniet-Girault, G Repetto… - … engineering and design, 2003 - Elsevier
The international Phebus Fission Product (FP) programme, initiated in 1988 and performed
by the French Institut de Radioprotection et de Sûreté Nucléaire (IRSN), investigates key …

Matrix swelling rate and cavity volume balance of UO2 fuels at high burn-up

J Spino, J Rest, W Goll, CT Walker - Journal of Nuclear Materials, 2005 - Elsevier
The low temperature matrix swelling of UO2 fuels was analysed as a function of burn-up,
taking into account changes in the fuel density, porosity and retained Xe concentration as …

Chemical interactions in water-cooled nuclear fuel: a thermochemical approach

EHP Cordfunke, RJM Konings - Journal of Nuclear Materials, 1988 - Elsevier
The complex equilibria in irradiated water-cooled nuclear fuel are discussed.
Thermochemical calculations have been performed to predict the chemical state of the …

The release of fission products from degraded UO2 fuel: Thermochemical aspects

EHP Cordfunke, RJM Konings - Journal of nuclear materials, 1993 - Elsevier
This review describes the chemical aspects of the release of the important fission products.
Their behaviour in the fuel, in the reactor coolant system (primary system), and during core …

Dynamics of irradiation-induced grain subdivision and swelling in U3Si2 and UO2 fuels

J Rest, GL Hofman - Journal of Nuclear materials, 1994 - Elsevier
Observations on low-temperature swelling of irradiated uranium silicide dispersion fuels
have shown that the growth of fission-gas bubbles is strongly affected by fission rate. The …

VICTORIA: a mechanistic model of radionuclide behavior in the reactor coolant system under severe accident conditions

TJ Heames, DA Williams, NA Johns, NM Chown… - 1990 - osti.gov
This document provides a description of a model of the radionuclide behavior in the reactor
coolant system (RCS) of a light water reactor during a severe accident. This document …

Kinetics of fission-gas-bubble-nucleated void swelling of the alpha-uranium phase of irradiated U-Zr and U-Pu-Zr fuel

J Rest - Journal of nuclear materials, 1993 - Elsevier
Bias-driven growth of voids is identified as a major swelling mechanism in the α-uranium
phase of irradiated U-Pu-Zr metal fuels being developed at Argonne National Laboratory for …

Fission products and nuclear fuel behaviour under severe accident conditions part 1: Main lessons learnt from the first VERDON test

Y Pontillon, E Geiger, C Le Gall, S Bernard… - Journal of Nuclear …, 2017 - Elsevier
This paper describes the first VERDON test performed at the end of September 2011 with
special emphasis on the behaviour of fission products (FP) and actinides during the …

Three-dimensional phase-field simulations of intragranular gas bubble evolution in irradiated U-Mo fuel

L Liang, ZG Mei, YS Kim, M Anitescu… - Computational Materials …, 2018 - Elsevier
The evolution of fission gas bubbles in irradiated materials plays a critical role in the
microstructural processes that leads to dimensional changes of U-Mo alloy fuels, eg, fuel …

[HTML][HTML] New insights into the Cs-Mo-O system: Experimental studies of the Cs2MoO4-MoO3 pseudo-binary system

AL Smith, J Vlieland, MC Pignié, M Abbink… - Thermochimica …, 2021 - Elsevier
The ternary cesium molybdates Cs 2 Mo 2 O 7, Cs 2 Mo 3 O 10, Cs 2 Mo 5 O 16 and Cs 2
Mo 7 O 22 have been synthesized in this work using a solid state route and their structures …