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Hydrogen diffusion under stress in Zircaloy: high-resolution neutron radiography and finite element modeling
Gong, W., Trtik, P., Valance, S., & Bertsch, J. (2018). Hydrogen diffusion under stress in Zircaloy: high-resolution neutron radiography and finite element modeling. Journal of Nuclear Materials, 508, 459-464. https://doi.org/10.1016/j.jnucmat.2018.05.079
Synchrotron X-ray diffraction investigations on strains in the oxide layer of an irradiated Zircaloy fuel cladding
Chollet, M., Valance, S., Abolhassani, S., Stein, G., Grolimund, D., Martin, M., & Bertsch, J. (2017). Synchrotron X-ray diffraction investigations on strains in the oxide layer of an irradiated Zircaloy fuel cladding. Journal of Nuclear Materials, 488, 181-190. https://doi.org/10.1016/j.jnucmat.2017.03.010
Corrosion and hydrogen uptake in zirconium claddings irradiated in light water reactors
Abolhassani, S., Bart, G., Bertsch, J., Grosse, M., Hallstadius, L., Hermann, A., … Wiese, H. (2015). Corrosion and hydrogen uptake in zirconium claddings irradiated in light water reactors. In R. J. Comstock & P. Barbéris (Eds.), Vol. STP1543. Zirconium in the nuclear industry. 17th international symposium (pp. 540-573). https://doi.org/10.1520/STP154320130007
Hydrides reorientation investigation of high burn-up PWR fuel cladding
Valance, S., & Bertsch, J. (2015). Hydrides reorientation investigation of high burn-up PWR fuel cladding. Journal of Nuclear Materials, 464, 371-381. https://doi.org/10.1016/j.jnucmat.2015.05.003
Hydrogen relocation kinetics within Zircaloy cladding tubes
Valance, S., Zemek, M., Bertsch, J., & Hellwig, C. (2015). Hydrogen relocation kinetics within Zircaloy cladding tubes. In TopFuel 2015: reactor fuel performance (p. (8 pp.). ENS European Nuclear Society.
Hydrides reorientation: from experimental investigation to modeling
Valance, S., & Bertsch, J. (2014). Hydrides reorientation: from experimental investigation to modeling. In H. Ishibashii (Ed.), Proceedings of 2014 water reactor fuel performance meeting, top fuel, LWR fuel performance meeting (WRFPM 2014) (p. 100110 (7 pp.). Sine nomine.
Neutron imaging investigations of the hydrogen related degradation of the mechanical properties of Zircaloy-4 cladding tubes
Grosse, M., Valance, S., Stuckert, J., Steinbrueck, M., Walter, M., Kaestner, A., … Santisteban, J. (2013). Neutron imaging investigations of the hydrogen related degradation of the mechanical properties of Zircaloy-4 cladding tubes. Materials research society symposium proceedings: Vol. 1528. (p. (6 pp.). Presented at the MRS fall meeting 2012. https://doi.org/10.1557/opl.2013.364
Hydrides in zirconium alloys – a characterization methods comparison
Valance, S., Bertsch, J., Bruetsch, R., Martin, M., Namburi, H., Portier, S., … Abolhassani, S. (2013). Hydrides in zirconium alloys – a characterization methods comparison. In LWR fuel performance meeting. TopFuel 2013 (pp. 359-366). American Nuclear Society.
In-situ neutron radiography determination of hydrogen concentration at a stress raiser
Valance, S., Grosse, M., Bertsch, J., Hartmann, S., Kaestner, A., & Santisteban, J. (2013). In-situ neutron radiography determination of hydrogen concentration at a stress raiser. In LWR fuel performance meeting. TopFuel 2013. Part 2 (pp. 980-985). American Nuclear Society.
Meso-scale analysis of the creep behavior of hydrogenated Zircaloy-4
Mallipudi, V. R., Valance, S., & Bertsch, J. (2012). Meso-scale analysis of the creep behavior of hydrogenated Zircaloy-4. Mechanics of Materials, 51, 15-28. https://doi.org/10.1016/j.mechmat.2012.03.003
Delayed hydride cracking in Zircaloy-2 fuel cladding tubes
Namburi, H. K., Valance, S., & Bertsch, J. (2012). Delayed hydride cracking in Zircaloy-2 fuel cladding tubes. In Top fuel 2012. Reactor fuel performance. Transactions (p. (7 pp.). European Nuclear Society.
A non-local formulation for level-set modelling
Valance, S. (2012). A non-local formulation for level-set modelling. European Journal of Computational Mechanics, 21(3-6), 385-396. https://doi.org/10.1080/17797179.2012.740588
Hydrides re-orientation and metallography analysis of five cycles irradiated fuel cladding samples
Zubler, R., Valance, S., Bertsch, J., & Urech, A. (2012). Hydrides re-orientation and metallography analysis of five cycles irradiated fuel cladding samples (p. (10 pp.). Presented at the 49th conference on hot laboratories and remote handling (HOTLAB 2012). .
Statistical analysis of hydride reorientation properties in irradiated Zircaloy-2
Valance, S., Bertsch, J., & Alam, A. M. (2011). Statistical analysis of hydride reorientation properties in irradiated Zircaloy-2. Journal of ASTM International, 8(1), 1-14. https://doi.org/10.1520/JAI102957