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Evaluation of mechanical properties of irradiated zirconium alloys in the vicinity of the metal-oxide interface
Colldeweih, A. W., Baris, A., Spätig, P., & Abolhassani, S. (2019). Evaluation of mechanical properties of irradiated zirconium alloys in the vicinity of the metal-oxide interface. Materials Science and Engineering A: Structural Materials: Properties, Microstructure and Processing, 742, 842-850. https://doi.org/10.1016/j.msea.2018.09.107
Influence of cracking direction on fracture mechanics during DHC of Zircaloy-2 cladding
Colldeweih, A. W., Gong, W., Zubler, R., Bertsch, J., & Trtik, P. (2019). Influence of cracking direction on fracture mechanics during DHC of Zircaloy-2 cladding. In Global/Top Fuel 2019. La Grange Park, IL, USA: American Nuclear Society (ANS).
Hydride characterization in Zircaloy-2 liner cladding after C-shaped ring compression tests
Duarte, L. I., Fagnoni, F., Zubler, R., Gong, W., Trtik, P., & Bertsch, J. (2019). Hydride characterization in Zircaloy-2 liner cladding after C-shaped ring compression tests. In Global/Top Fuel 2019. La Grange Park, IL, USA: American Nuclear Society (ANS).
Hydrides in irradiated liner cladding - local and in-depth concentration determination by neutron radiography
Duarte, L. I., Fagnoni, F., Zubler, R., Gong, W., Trtik, P., & Bertsch, J. (2019). Hydrides in irradiated liner cladding - local and in-depth concentration determination by neutron radiography. In Global/Top Fuel 2019. La Grange Park, IL, USA: American Nuclear Society (ANS).
Anisotropic influence of hydrides on Zircaloy fatigue
Gong, W., Mille, M., Zubler, R., & Bertsch, J. (2019). Anisotropic influence of hydrides on Zircaloy fatigue. In Global/Top Fuel 2019. La Grange Park, IL, USA: American Nuclear Society (ANS).
Hydride reorientation and redistribution under non-uniform stress
Gong, W., Trtik, P., Zubler, R., & Bertsch, J. (2019). Hydride reorientation and redistribution under non-uniform stress. In Global/Top Fuel 2019. La Grange Park, IL, USA: American Nuclear Society (ANS).
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
Non-empirical calculation of X-ray magnetic circular dichroism in lanthanide compounds
Ramanantoanina, H., Studniarek, M., Daffé, N., & Dreiser, J. (2019). Non-empirical calculation of X-ray magnetic circular dichroism in lanthanide compounds. Chemical Communications, 55(20), 2988-2991. https://doi.org/10.1039/C8CC09321K
Transmission electron microscopy examinations of metal-oxide interface of zirconium-based alloys irradiated in halden reactor-IFA-638
Abolhassani, S., Proff, C., Veleva, L., Karlsen, T. M., Bennett, P., Oberländer, B., … Garde, A. M. (2018). Transmission electron microscopy examinations of metal-oxide interface of zirconium-based alloys irradiated in halden reactor-IFA-638. In R. J. Comstock & A. T. Motta (Eds.), Vol. STP 1597. ASTM Special Technical Publication. https://doi.org/10.1520/STP159720160039
Causes of increased corrosion and hydrogen uptake of zircaloy-2 cladding at high burnups – a comparative study of the chemical composition of a 3 cycle and a 9 cycle cladding
Baris, A., Abolhassani, S., Grabherr, R., Restani, R., Schäublin, R., Chiu, Y. L., … Limbäck, M. (2018). Causes of increased corrosion and hydrogen uptake of zircaloy-2 cladding at high burnups – a comparative study of the chemical composition of a 3 cycle and a 9 cycle cladding. In Topfuel 2018. Part 5. Brussels: European Nuclear Society.
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
Observation of crack microstructure in oxides and its correlation to oxidation and hydrogen-uptake by 3D FIB Tomography–case of Zr-ZrO<sub>2</sub> in reactor
Baris, A., Abolhassani, S., Chiu, Y. L., & Evans, H. E. (2018). Observation of crack microstructure in oxides and its correlation to oxidation and hydrogen-uptake by 3D FIB Tomography–case of Zr-ZrO2 in reactor. Materials at High Temperatures, 35(1-3), 14-21. https://doi.org/10.1080/09603409.2017.1392412
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
Zirconium liner cladding materials: hydrogen diffusion to the liner under cooling/stress gradient
Gong, W., Zubler, R., Trtik, P., & Bertsch, J. (2018). Zirconium liner cladding materials: hydrogen diffusion to the liner under cooling/stress gradient. Presented at the 2018 MRS Spring Meeting. Phoenix, Arizona, USA.
Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging
Grosse, M., Santisteban, J. R., Bertsch, J., Schillinger, B., Kaestner, A., Daymond, M. R., & Kardjilov, N. (2018). Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging. Kerntechnik, 83(6), 495-501. https://doi.org/10.3139/124.110946
Chemical state and atomic scale environment of nickel in the corrosion layer of irradiated Zircaloy-2 at a burn-up around 45 MWd/kg
Kuri, G., Ramanantoanina, H., Bertsch, J., Martin, M., & Panas, I. (2018). Chemical state and atomic scale environment of nickel in the corrosion layer of irradiated Zircaloy-2 at a burn-up around 45 MWd/kg. Corrosion Science, 143, 200-211. https://doi.org/10.1016/j.corsci.2018.08.032
Analysis of the U L&lt;sub&gt;3&lt;/sub&gt;-edge X-ray absorption spectra in UO&lt;sub&gt;2&lt;/sub&gt; using molecular dynamics simulations
Bocharov, D., Chollet, M., Krack, M., Bertsch, J., Grolimund, D., Martin, M., … Kotomin, E. (2017). Analysis of the U L3-edge X-ray absorption spectra in UO2 using molecular dynamics simulations. Progress in Nuclear Energy, 94, 187-193. https://doi.org/10.1016/j.pnucene.2016.07.017
New insights in the fuel grain subdivision during in-plant irradiation up to high burn-up
Chollet, M., Cozzo, C., Bertsch, J., Martin, M., Grolimund, D., & Samson, V. A. (2017). New insights in the fuel grain subdivision during in-plant irradiation up to high burn-up. Presented at the Water reactor fuel performance meeting 2017 (WRFPM 2017). Jeju, Korea.
Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels
Chollet, M., Cozzo, C., & Bertsch, J. (2017). Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels. EPJ Nuclear Sciences and Technologies, 3, 3. https://doi.org/10.1051/epjn/2016040
Quantifying the stress field of hydride precipitation by mu-XRD tomography
Chollet, M., Gong, W., Ferreira Sanchez, D., Samson, V. A., & Bertsch, J. (2017). Quantifying the stress field of hydride precipitation by mu-XRD tomography. Presented at the Water reactor fuel performance meeting 2017 (WRFPM 2017). Jeju, Korea.
 

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