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DBTT shift of Optifer-IX, Eurofer 97 and MA956 steels after irradiation evaluated with small punch tests
Yao, C. F., & Dai, Y. (2021). DBTT shift of Optifer-IX, Eurofer 97 and MA956 steels after irradiation evaluated with small punch tests. Journal of Nuclear Materials, 544, 152725 (9 pp.). https://doi.org/10.1016/j.jnucmat.2020.152725
In-beam creep of SiC<sub>f</sub>/SiC minicomposites under uniaxial tensile loading
Chen, J., Jacques, S., Barthe, M. F., Zhang, C., & Desgardin, P. (2020). In-beam creep of SiCf/SiC minicomposites under uniaxial tensile loading. Journal of Nuclear Materials, 533, 152086 (7 pp.). https://doi.org/10.1016/j.jnucmat.2020.152086
Oxygen potential calculations for conventional and Cr-doped UO<sub>2</sub> fuels based on solid solution thermodynamics
Curti, E., & Kulik, D. A. (2020). Oxygen potential calculations for conventional and Cr-doped UO2 fuels based on solid solution thermodynamics. Journal of Nuclear Materials, 534, 152140 (18 pp.). https://doi.org/10.1016/j.jnucmat.2020.152140
Characterization of the conductivity of metal-oxide interface of zirconium based fuel cladding at low and high burnups
Hawes, J., Baris, A., Chiu, Y. L., & Abolhassani, S. (2020). Characterization of the conductivity of metal-oxide interface of zirconium based fuel cladding at low and high burnups. Journal of Nuclear Materials, 534, 152133 (12 pp.). https://doi.org/10.1016/j.jnucmat.2020.152133
Evaporation of materials from the molten salt reactor fuel under elevated temperatures
Kalilainen, J., Nichenko, S., & Krepel, J. (2020). Evaporation of materials from the molten salt reactor fuel under elevated temperatures. Journal of Nuclear Materials, 533, 152134 (13 pp.). https://doi.org/10.1016/j.jnucmat.2020.152134
Pt catalytic effects on the corrosion and hydrogen chemisorption properties of Zircaloy-2
Rowthu, S., Grundler, P. V., Müller, E., & Ritter, S. (2020). Pt catalytic effects on the corrosion and hydrogen chemisorption properties of Zircaloy-2. Journal of Nuclear Materials, 544, 152716 (15 pp.). https://doi.org/10.1016/j.jnucmat.2020.152716
Experimental validation of tensile properties measured with thick samples taken from MEGAPIE target
Saito, S., Suzuki, K., Hatakeyama, Y., Suzuki, M., & Dai, Y. (2020). Experimental validation of tensile properties measured with thick samples taken from MEGAPIE target. Journal of Nuclear Materials, 534, 152146 (16 pp.). https://doi.org/10.1016/j.jnucmat.2020.152146
Hydrogen diffusion and precipitation in duplex zirconium nuclear fuel cladding quantified by high-resolution neutron imaging
Gong, W., Trtik, P., Colldeweih, A. W., Duarte, L. I., Grosse, M., Lehmann, E., & Bertsch, J. (2019). Hydrogen diffusion and precipitation in duplex zirconium nuclear fuel cladding quantified by high-resolution neutron imaging. Journal of Nuclear Materials, 526, 151757 (13 pp.). https://doi.org/10.1016/j.jnucmat.2019.151757
Mechanical properties of tungsten irradiated with high-energy protons and spallation neutrons
Habainy, J., Dai, Y., Lee, Y., & Iyengar, S. (2019). Mechanical properties of tungsten irradiated with high-energy protons and spallation neutrons. Journal of Nuclear Materials, 514, 189-195. https://doi.org/10.1016/j.jnucmat.2018.12.003
The measurement of Ag/In/Cd release under air-ingress conditions in the QUENCH-18 bundle test
Kalilainen, J., Lind, T., Stuckert, J., Bergfeldt, T., Sippula, O., & Jokiniemi, J. (2019). The measurement of Ag/In/Cd release under air-ingress conditions in the QUENCH-18 bundle test. Journal of Nuclear Materials, 517, 315-327. https://doi.org/10.1016/j.jnucmat.2019.02.021
Experimental comparison of the (ODS)EUROFER steels implanted by helium ions and irradiated in spallation neutron target
Krsjak, V., Degmova, J., Simeg Veternikova, J., Yao, C. F., & Dai, Y. (2019). Experimental comparison of the (ODS)EUROFER steels implanted by helium ions and irradiated in spallation neutron target. Journal of Nuclear Materials, 523, 51-55. https://doi.org/10.1016/j.jnucmat.2019.05.044
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
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
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
Dislocation loops in ultra-high purity Fe(Cr) alloys after 7.2 MeV proton irradiation
Chen, J., Duval, F., Jung, P., Schäublin, R., Gao, N., & Barthe, M. F. (2018). Dislocation loops in ultra-high purity Fe(Cr) alloys after 7.2 MeV proton irradiation. Journal of Nuclear Materials, 503, 81-90. https://doi.org/10.1016/j.jnucmat.2018.02.042
Microstructural changes of ferritic/martensitic steels after irradiation in spallation target environments
Dai, Y., Krsjak, V., Kuksenko, V., & Schäublin, R. (2018). Microstructural changes of ferritic/martensitic steels after irradiation in spallation target environments. Journal of Nuclear Materials, 511, 508-522. https://doi.org/10.1016/j.jnucmat.2018.09.028
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
Fatigue properties of tungsten from two different processing routes
Habainy, J., Lövberg, A., Iyengar, S., Lee, Y., & Dai, Y. (2018). Fatigue properties of tungsten from two different processing routes. Journal of Nuclear Materials, 506, 83-91. https://doi.org/10.1016/j.jnucmat.2017.10.061
Formation of oxide layers on tungsten at low oxygen partial pressures
Habainy, J., Iyengar, S., Surreddi, K. B., Lee, Y., & Dai, Y. (2018). Formation of oxide layers on tungsten at low oxygen partial pressures. Journal of Nuclear Materials, 506, 26-34. https://doi.org/10.1016/j.jnucmat.2017.12.018
Thermal diffusivity of tungsten irradiated with protons up to 5.8 dpa
Habainy, J., Dai, Y., Lee, Y., & Iyengar, S. (2018). Thermal diffusivity of tungsten irradiated with protons up to 5.8 dpa. Journal of Nuclear Materials, 509, 152-157. https://doi.org/10.1016/j.jnucmat.2018.06.041
 

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