References
- A.-M. Alvarez Holston, K. Kitano, Kallstrom R., Wikmark G., Arimescu I., Schrire D., "Cladding mechanical assessment and application in modelling", Top Fuel 2006, Salamanca, Spain (2006).
- Kallstrom R., "SCIP, Task 0; Ramp test results", Report Studsvik-SCIP-42 (2005).
- Struzik C., Moyne M., Piron J.-P., "High burn-up modelling of UO2 and MOX fuel with METEOR/TRANSURANUS version 1.5", ANS International Topical Meeting on Light Water Reactor Fuel Performances, Portland (1997).
- Thouvenin G., Michel B., Sercombe J., Plancq D., Thevenin P., "Multidimensional modeling of a ramp test with the PWR fuel performance code ALCYONE", International Meeting on LWR Fuel Performance, San Francisco, USA (2007).
- Bentejac F., "TOUTATIS an application of the CAST3M finite element code for PCI three dimensional modeling", International seminar on PCI, Aix en Provence, France (2004).
- Plancq D., "PLEIADES: a unified environment for multi-dimensional fuel performance modelling", International Meeting on LWR Fuel Performance, Florida (2004).
- Michel B., Sercombe J., Thouvenin G., Chatelet R., << 3D fuel cracking modelling in pellet cladding mechanical interaction", Engineering Fracture Mechanics 75, 3581-3598 (2008). https://doi.org/10.1016/j.engfracmech.2006.12.014
- Michel B., "3D Fuel Modelling: Multi physic coupling formulation between gaseous swelling and mechanical behaviour", in preparation (2009).
- Ledergerber G., Abolhassani S., Limback M., Lundmark R.J., Magnusson K.A., << Characterization of high burn up fuel for safety related fuel testing >>, Journal of Nuclear Science and Technology, 43 (9), 1006-1014 (2006). https://doi.org/10.3327/jnst.43.1006
- Garcia P., Struzik C., Agard M., Louche V., << Mono-dimensional mechanical modelling of fuel rods under normal and off-normal operating conditions >>, Nuclear Eng. And Design, 216, 183-201 (2002). https://doi.org/10.1016/S0029-5493(02)00059-6
- Roberts G., "The concentration of stress in cladding produced by the expansion of cracked fuel pellets", Nuclear Eng. And Design, 47, 257-266 (1978). https://doi.org/10.1016/0029-5493(78)90068-7
- Brochard J., Bentejac F., Hourdequin N., Seror S., Verdeau C., Fandeur O., Lansiard S., Verpeaux P., "Modelling of Pellet Cladding Interaction in PWR fuel", Transactions of SMIRT 16, Washington DC (2001).
- Cox B., << Pellet-Clad Interaction (PCI) failures of zirconium alloy fuel cladding - a review", Journal of Nuclear Materials, 172, 249-292 (1990). https://doi.org/10.1016/0022-3115(90)90282-R
- Nonon C., Lansiart S., Struzik C., Plancq D., Martin S., Decroix G.M., Rabouille O., Beguin S., Julien B., << Differential PCI behaviour of PWR fuel rods under transient conditions >>, Proc. Of the Int. Meeting on LWR Fuel Performance, Orlando, USA (2004).
- Mougel C., Verhaeghe B., Verdeau C., Lansiart S., Beguin S., Julien B., << Power ramping in the Osiris reactor : databaseanalysis for standard UO2 fuel with Zy-4 cladding", Proc. Of the Pellet-clad Interaction in Water Reactor Fuels Seminar, Aix-en-Provence, France (2004).
- Michel B., Sercombe J., Thouvenin G., << A new phenomenological criterion for Pellet Cladding Interaction rupture", in Press, Nuclear Eng. and Design, 238, 1612-1628 (2008). https://doi.org/10.1016/j.nucengdes.2008.01.012
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- Simulation of Pellet-Cladding Interaction with the PLEIADES Fuel Performance Software Environment vol.182, pp.2, 2013, https://doi.org/10.13182/NT13-A16424