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Hydrogen enhanced localized plasticity in zirconium as observed by digital image correlation
Fagnoni, F., Kursun, E. .C., Busi, M., Konarski, P., Yetik, O., Spolenak, R., … Duarte, L. I. (2024). Hydrogen enhanced localized plasticity in zirconium as observed by digital image correlation. Journal of Nuclear Materials, 590, 154873 (10 pp.). https://doi.org/10.1016/j.jnucmat.2023.154873
Effect of material inhomogeneity on constraint loss measured with subsized C(T) fracture specimens of a reactor pressure vessel steel
Jiang, D., Spätig, P., & Seifert, H. P. (2024). Effect of material inhomogeneity on constraint loss measured with subsized C(T) fracture specimens of a reactor pressure vessel steel. Journal of Nuclear Materials, 588, 154801 (9 pp.). https://doi.org/10.1016/j.jnucmat.2023.154801
APT characterization of irradiation effects on MX phase in reduced-activation ferritic/martensitic steels
Cui, L., Dai, Y., Gerstl, S. S. A., & Pounchon, M. A. (2023). APT characterization of irradiation effects on MX phase in reduced-activation ferritic/martensitic steels. Journal of Nuclear Materials, 573, 154121 (10 pp.). https://doi.org/10.1016/j.jnucmat.2022.154121
Hydrogen diffusion in zirconium cladding alloys with an inner liner as quantified by neutron radiography and nanoindentation
Fagnoni, F., Trtik, P., Wheeler, J. M., Zubler, R., Bertsch, J., & Duarte, L. I. (2023). Hydrogen diffusion in zirconium cladding alloys with an inner liner as quantified by neutron radiography and nanoindentation. Journal of Nuclear Materials, 584, 154574 (12 pp.). https://doi.org/10.1016/j.jnucmat.2023.154574
Nitriding model for zirconium based fuel cladding in severe accident codes
Jäckel, B. S., Birchley, J. C., Lind, T., Steinbrück, M., & Park, S. (2023). Nitriding model for zirconium based fuel cladding in severe accident codes. Journal of Nuclear Materials, 582, 154466 (7 pp.). https://doi.org/10.1016/j.jnucmat.2023.154466
Determination of the hydrogen heat of transport in Zircaloy-4
Kang, S., Huang, P. H., Petrov, V., Manera, A., Ahn, T., Kammenzind, B., & Motta, A. T. (2023). Determination of the hydrogen heat of transport in Zircaloy-4. Journal of Nuclear Materials, 573, 154122 (10 pp.). https://doi.org/10.1016/j.jnucmat.2022.154122
Analysis of thermal fuel behaviour under steady-state irradiation using selected cases of the IAEA CRP FUMEX
Khvostov, G. (2023). Analysis of thermal fuel behaviour under steady-state irradiation using selected cases of the IAEA CRP FUMEX. Journal of Nuclear Materials, 584, 154589 (8 pp.). https://doi.org/10.1016/j.jnucmat.2023.154589
Calibration and validation of thermal fuel behaviour models based on the first case of the first IAEA CRP FUMEX
Khvostov, G. (2023). Calibration and validation of thermal fuel behaviour models based on the first case of the first IAEA CRP FUMEX. Journal of Nuclear Materials, 584, 154588 (11 pp.). https://doi.org/10.1016/j.jnucmat.2023.154588
Modeling of hydrogen behavior in liner claddings
Konarski, P., Cozzo, C., Khvostov, G., & Ferroukhi, H. (2023). Modeling of hydrogen behavior in liner claddings. Journal of Nuclear Materials, 573, 154125 (11 pp.). https://doi.org/10.1016/j.jnucmat.2022.154125
Fission products at the fuel-cladding interface of PWR fuel rods: morphological and chemical study
Schneider, C., Fayette, L., Zacharie-Aubrun, I., Blay, T., Onofri-Marroncle, C., Sabathier, C., … Chevalier, S. (2023). Fission products at the fuel-cladding interface of PWR fuel rods: morphological and chemical study. Journal of Nuclear Materials, 585, 154600 (17 pp.). https://doi.org/10.1016/j.jnucmat.2023.154600
The effect of potassium hydroxide primary water chemistry on the IASCC behavior of 304 stainless steel
Chen, K., Ickes, M. R., Burke, M. A., & Was, G. S. (2022). The effect of potassium hydroxide primary water chemistry on the IASCC behavior of 304 stainless steel. Journal of Nuclear Materials, 558, 153323 (11 pp.). https://doi.org/10.1016/j.jnucmat.2021.153323
Delayed hydride cracking in Zircaloy-2 with and without liner at various temperatures investigated by high-resolution neutron radiography
Colldeweih, A. W., Fagnoni, F., Trtik, P., Zubler, R., Pouchon, M. A., & Bertsch, J. (2022). Delayed hydride cracking in Zircaloy-2 with and without liner at various temperatures investigated by high-resolution neutron radiography. Journal of Nuclear Materials, 561, 153549 (12 pp.). https://doi.org/10.1016/j.jnucmat.2022.153549
Effect of temperature and hydrogen concentration on the threshold stress intensity factor of radial delayed hydride cracking in fuel cladding
Colldeweih, A. W., & Bertsch, J. (2022). Effect of temperature and hydrogen concentration on the threshold stress intensity factor of radial delayed hydride cracking in fuel cladding. Journal of Nuclear Materials, 565, 153737 (11 pp.). https://doi.org/10.1016/j.jnucmat.2022.153737
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
Comparative study of deuterium retention and vacancy content of self-ion irradiated tungsten
Hollingsworth, A., Barthe, M. F., Lavrentiev, M. Y., Derlet, P. M., Dudarev, S. L., Mason, D. R., … Morellec, A. (2022). Comparative study of deuterium retention and vacancy content of self-ion irradiated tungsten. Journal of Nuclear Materials, 558, 153373 (13 pp.). https://doi.org/10.1016/j.jnucmat.2021.153373
Modelling effects of transient FGR in LWR fuel rods during a LOCA
Khvostov, G. (2022). Modelling effects of transient FGR in LWR fuel rods during a LOCA. Journal of Nuclear Materials, 559, 153446 (26 pp.). https://doi.org/10.1016/j.jnucmat.2021.153446
A novel method for radial hydride analysis in zirconium alloys: HAPPy
Maric, M., Thomas, R., Nunez-Iglesias, J., Atkinson, M., Bertsch, J., Frankel, P., … Shanthraj, P. (2022). A novel method for radial hydride analysis in zirconium alloys: HAPPy. Journal of Nuclear Materials, 559, 153442 (14 pp.). https://doi.org/10.1016/j.jnucmat.2021.153442
Effect of the inner liner on the hydrogen distribution of zircaloy-2 nuclear fuel claddings
Duarte, L. I., Fagnoni, F., Zubler, R., Gong, W., Trtik, P., & Bertsch, J. (2021). Effect of the inner liner on the hydrogen distribution of zircaloy-2 nuclear fuel claddings. Journal of Nuclear Materials, 557, 153284 (6 pp.). https://doi.org/10.1016/j.jnucmat.2021.153284
Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling
Konarski, P., Cozzo, C., Khvostov, G., & Ferroukhi, H. (2021). Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling. Journal of Nuclear Materials, 555, 153138 (26 pp.). https://doi.org/10.1016/j.jnucmat.2021.153138
Characterizing accelerated precipitation in proton irradiated steel
Laver, M., Connolly, B. J., Cooper, C., Kohlbrecher, J., Samothrakitis, S., & Wilford, K. (2021). Characterizing accelerated precipitation in proton irradiated steel. Journal of Nuclear Materials, 557, 153195 (15 pp.). https://doi.org/10.1016/j.jnucmat.2021.153195
 

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