, Nuclear Fuel Safety Criteria
No clad lift-off" criterion and associated methodology developed by EDF and Framatome-ANP on the basis of IFA-610 experiments, EHPG meeting, 2005. ,
Rod overpressure / liftoff testing at Halden -In-pile data and analysis, Journal of Nuclear Science and Technology, vol.43, pp.1037-1044, 2006. ,
Simulation of Pellet-Cladding Interaction with the PLEIADES fuel performance software environment, Nuclear Technology ,
Thermo-mechanical modelling of PWR fuel with ALCYONE, Proceedings of the 2011 Water Reactor Fuel Performance Meeting, 2011. ,
3D modelling of strain concentration due to PCI within the fuel code ALCYONE, Proceedings of Top Fuel, 2013. ,
1D and 3D modelling of PCMI during a RIA with ALCYONE V1.1, Top Fuel, 2010. ,
Stress concentration during pellet cladding interaction: Comparison of closed-form solutions with 2D(r,?) finite element simulations, Nuclear Engineering and Design, vol.260, pp.175-187, 2013. ,
Validation of fuel performance CEA code ALCYONE, scheme 1D, on extensive database, Proceedings of Top Fuel, 2012. ,
The lift-off experiment with MOX fuel rod in IFA-610.2 -Initial results, 1999. ,
The lift-off experiment with MOX fuel in IFA-610.2 -Results of the second cycle, 1999. ,
The lift-off experiments, IFA-610.3 (UO2), and IFA-610.4 (MOX) -Evaluation of in-pile measurement data, 2001. ,
The lift-off experiment IFA-610.5 with UO2 fuel rod -Evaluation of in-pile results, 2002. ,
The lift-off experiment IFA-610.7 with high burn-up PWR MOX fuel rod -In-pile results from 3-cycles irradiation, 2006. ,
The revised URGAP model to describe the gap conductance between fuel and cladding, Nuclear Eng. and Design, vol.103, pp.215-221, 1987. ,