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Examination of the chemical composition of irradiated zirconium based fuel claddings at the metal/oxide interface by TEM
Abolhassani, S., Bart, G., & Jakob, A. (2010). Examination of the chemical composition of irradiated zirconium based fuel claddings at the metal/oxide interface by TEM. Journal of Nuclear Materials, 399(1), 1-12. https://doi.org/10.1016/j.jnucmat.2009.10.060
In situ study of the oxidation of Zircaloy-4 by ESEM
Abolhassani, S., Dadras, M., Leboeuf, M., & Gavillet, D. (2003). In situ study of the oxidation of Zircaloy-4 by ESEM. Journal of Nuclear Materials, 321(1), 70-77. https://doi.org/10.1016/S0022-3115(03)00201-0
Evaporation of mercury impurity from liquid lead-bismuth eutectic
Aerts, A., Danaci, S., Gonzalez Prieto, B., Van Den Bosch, J., & Neuhausen, J. (2014). Evaporation of mercury impurity from liquid lead-bismuth eutectic. Journal of Nuclear Materials, 448(1-3), 276-281. https://doi.org/10.1016/j.jnucmat.2014.02.013
Critical evaluation of the small punch test as a screening procedure for mechanical properties
Altstadt, E., Ge, H. E., Kuksenko, V., Serrano, M., Houska, M., Lasan, M., … Dai, Y. (2016). Critical evaluation of the small punch test as a screening procedure for mechanical properties. Journal of Nuclear Materials, 472, 186-195. https://doi.org/10.1016/j.jnucmat.2015.07.029
Evaluation of thermal conductivity of zirconia-based inert matrix fuel by molecular dynamics simulation
Arima, T., Yamasaki, S., Yamahira, K., Idemitsu, K., Inagaki, Y., & Degueldre, C. (2006). Evaluation of thermal conductivity of zirconia-based inert matrix fuel by molecular dynamics simulation. Journal of Nuclear Materials, 352(1-3), 309-317. https://doi.org/10.1016/j.jnucmat.2006.02.066
Depinning transition of a dislocation line in ferritic oxide strengthened steels
Bakó, B., Zaiser, M., Weygand, D., Samaras, M., & Hoffelner, W. (2009). Depinning transition of a dislocation line in ferritic oxide strengthened steels. Journal of Nuclear Materials, 385(2), 284-287. https://doi.org/10.1016/j.jnucmat.2008.12.003
The influence of helium bubbles on the critical resolved shear stress of dispersion strengthened alloys
Bakó, B., Samaras, M., Weygand, D., Chen, J., Gumbsch, P., & Hoffelner, W. (2009). The influence of helium bubbles on the critical resolved shear stress of dispersion strengthened alloys. Journal of Nuclear Materials, 386-388(C), 112-114. https://doi.org/10.1016/j.jnucmat.2008.12.074
Chemical and microstructural characterization of a 9 cycle Zircaloy-2 cladding using EPMA and FIB tomography
Baris, A., Restani, R., Grabherr, R., Chiu, Y. L., Evans, H. E., Ammon, K., … Abolhassani, S. (2018). Chemical and microstructural characterization of a 9 cycle Zircaloy-2 cladding using EPMA and FIB tomography. Journal of Nuclear Materials, 504, 144-160. https://doi.org/10.1016/j.jnucmat.2018.01.065
Fuel and fission product behaviour in early phases of a severe accident. Part I: experimental results of the PHEBUS FPT2 test
Barrachin, M., Gavillet, D., Dubourg, R., & De Bremaecker, A. (2014). Fuel and fission product behaviour in early phases of a severe accident. Part I: experimental results of the PHEBUS FPT2 test. Journal of Nuclear Materials, 453(1-3), 340-354. https://doi.org/10.1016/j.jnucmat.2014.05.079
AC-3-irradiation test of sphere-pac and pellet (U,Pu)C fuel in the US Fast Flux Test Facility
Bart, G., Botta, F. B., Hoth, C. W., Ledergerber, G., Mason, R. E., & Stratton, R. W. (2008). AC-3-irradiation test of sphere-pac and pellet (U,Pu)C fuel in the US Fast Flux Test Facility. Journal of Nuclear Materials, 376(1), 47-59. https://doi.org/10.1016/j.jnucmat.2008.01.022
Experimental assessment of thermophysical properties of (Pu,Zr)N
Basini, V., Ottaviani, J. P., Richaud, J. C., Streit, M., & Ingold, F. (2005). Experimental assessment of thermophysical properties of (Pu,Zr)N. Journal of Nuclear Materials, 344(1-3), 186-190. https://doi.org/10.1016/j.jnucmat.2005.04.040
Analysis of neutron attenuation in boron-alloyed stainless steel with neutron radiography and JEN-3 gauge
Bastürk, M., Arztmann, J., Jerlich, W., Kardjilov, N., Lehmann, E., & Zawisky, M. (2005). Analysis of neutron attenuation in boron-alloyed stainless steel with neutron radiography and JEN-3 gauge. Journal of Nuclear Materials, 341(2-3), 189-200. https://doi.org/10.1016/j.jnucmat.2005.02.003
MEGAPIE, a 1 MW pilot experiment for a liquid metal spallation target
Bauer, G. S., Salvatores, M., & Heusener, G. (2001). MEGAPIE, a 1 MW pilot experiment for a liquid metal spallation target. Journal of Nuclear Materials, 296(1-3), 17-33. https://doi.org/10.1016/S0022-3115(01)00561-X
Summary of the fourth international workshop on spallation materials technology (IWSMT-4)
Bauer, G. S., Dai, Y., Maloy, S., Mansur, L. K., & Ullmaier, H. (2001). Summary of the fourth international workshop on spallation materials technology (IWSMT-4). Journal of Nuclear Materials, 296(1-3), 321-325. https://doi.org/10.1016/S0022-3115(01)00568-2
A DFT study of the stability of SIAs and small SIA clusters in the vicinity of solute atoms in Fe
Becquart, C. S., Ngayam Happy, R., Olsson, P., & Domain, C. (2018). A DFT study of the stability of SIAs and small SIA clusters in the vicinity of solute atoms in Fe. Journal of Nuclear Materials, 500, 92-109. https://doi.org/10.1016/j.jnucmat.2017.12.022
Transmutation characteristics in thermal and fast neutron spectra: application to americium
Berthou, V., Degueldre, C., & Magill, J. (2003). Transmutation characteristics in thermal and fast neutron spectra: application to americium. Journal of Nuclear Materials, 320(1-2), 156-162. https://doi.org/10.1016/S0022-3115(03)00183-1
Linking atomic and mesoscopic scales for the modelling of the transport properties of uranium dioxide under irradiation
Bertolus, M., Freyss, M., Dorado, B., Martin, G., Hoang, K., Maillard, S., … Behera, R. K. (2015). Linking atomic and mesoscopic scales for the modelling of the transport properties of uranium dioxide under irradiation. Journal of Nuclear Materials, 462, 475-495. https://doi.org/10.1016/j.jnucmat.2015.02.026
Crack resistance curves determination of tube cladding material
Bertsch, J., & Hoffelner, W. (2006). Crack resistance curves determination of tube cladding material. Journal of Nuclear Materials, 352(1-3), 116-125. https://doi.org/10.1016/j.jnucmat.2006.02.045
Calculations on fission gas behaviour in the high burnup structure
Blair, P., Romano, A., Hellwig, C., & Chawla, R. (2006). Calculations on fission gas behaviour in the high burnup structure. Journal of Nuclear Materials, 350(3), 232-239. https://doi.org/10.1016/j.jnucmat.2006.01.006
Determination of very low concentrations of hydrogen in zirconium alloys by neutron imaging
Buitrago, N. L., Santisteban, J. R., Tartaglione, A., Marín, J., Barrow, L., Daymond, M. R., … Kabra, S. (2018). Determination of very low concentrations of hydrogen in zirconium alloys by neutron imaging. Journal of Nuclear Materials, 503, 98-109. https://doi.org/10.1016/j.jnucmat.2018.02.048
 

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