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Zirconium hydride phase mapping in Zircaloy-2 cladding after delayed hydride cracking
Colldeweih, A. W., Makowska, M. G., Tabai, O., Sanchez, D. F., & Bertsch, J. (2023). Zirconium hydride phase mapping in Zircaloy-2 cladding after delayed hydride cracking. Materialia, 27, 101689 (10 pp.). https://doi.org/10.1016/j.mtla.2023.101689
Hydrogen diffusion and precipitation under non-uniform stress in duplex zirconium nuclear fuel cladding investigated by high-resolution neutron imaging
Gong, W., Trtik, P., Ma, F., Jia, Y., Li, J., & Bertsch, J. (2022). Hydrogen diffusion and precipitation under non-uniform stress in duplex zirconium nuclear fuel cladding investigated by high-resolution neutron imaging. Journal of Nuclear Materials, 570, 153971 (10 pp.). https://doi.org/10.1016/j.jnucmat.2022.153971
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
Cyclic softening in annealed Zircaloy-2: role of edge dislocation dipoles and vacancies
Sudhakar Rao, G., Singh, S. R., Krsjak, V., & Singh, V. (2018). Cyclic softening in annealed Zircaloy-2: role of edge dislocation dipoles and vacancies. Journal of Nuclear Materials, 502, 154-160. https://doi.org/10.1016/j.jnucmat.2018.02.011
Wavelength dependent neutron transmission and radiography investigations of the high temperature behaviour of materials applied in nuclear fuel and control rod claddings
Grosse, M., Steinbrueck, M., & Kaestner, A. (2011). Wavelength dependent neutron transmission and radiography investigations of the high temperature behaviour of materials applied in nuclear fuel and control rod claddings. Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 651(1), 315-319. https://doi.org/10.1016/j.nima.2011.02.102
Kinetics of hydrogen absorption and release in zirconium alloys during steam oxidation
Grosse, M., Steinbrueck, M., Lehmann, E., & Vontobel, P. (2008). Kinetics of hydrogen absorption and release in zirconium alloys during steam oxidation. Oxidation of Metals, 70(3-4), 149-162. https://doi.org/10.1007/s11085-008-9113-2
TEM examinations of the metal-oxide interface of zirconium based alloys irradiated in a pressurized water reactor
Abolhassani, S., Restani, R., Rebac, T., Groeschel, F., Hoffelner, W., Bart, G., … Aeschbach, F. (2005). TEM examinations of the metal-oxide interface of zirconium based alloys irradiated in a pressurized water reactor. Journal of ASTM International, 2(6), 1-25. https://doi.org/10.1520/JAI12390