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A NEA review on innovative structural materials solutions, including advanced manufacturing processes for nuclear applications based on technology readiness assessment
Balbaud, F., Cabet, C., Cornet, S., Dai, Y., Gan, J., Hernández Mayoral, M., … Weisenburger, A. (2021). A NEA review on innovative structural materials solutions, including advanced manufacturing processes for nuclear applications based on technology readiness assessment. Nuclear Materials and Energy, 27, 101006 (13 pp.). https://doi.org/10.1016/j.nme.2021.101006
Stress corrosion crack initiation testing with tapered specimens in high-temperature water - results of a collaborative research project
Bosch, R. W., Ritter, S., Herbst, M., Kilian, R., Burke, M. G., Duff, J., … Zajec, B. (2021). Stress corrosion crack initiation testing with tapered specimens in high-temperature water - results of a collaborative research project. Corrosion Engineering Science and Technology, 56(2), 103-118. https://doi.org/10.1080/1478422X.2020.1815460
Characterization of austenitic stainless steels with regard to environmentally assisted fatigue in simulated light water reactor conditions
Bruchhausen, M., Dundulis, G., McLennan, A., Arrieta, S., Austin, T., Cicero, R. n, … Vankeerberghen, M. (2021). Characterization of austenitic stainless steels with regard to environmentally assisted fatigue in simulated light water reactor conditions. Metals, 11(2), 307 (20 pp.). https://doi.org/10.3390/met11020307
Role of mean stress on fatigue behavior of a 316L austenitic stainless steel in LWR and air environments
Chen, W., Spätig, P., & Seifert, H. P. (2021). Role of mean stress on fatigue behavior of a 316L austenitic stainless steel in LWR and air environments. International Journal of Fatigue, 145, 106111 (14 pp.). https://doi.org/10.1016/j.ijfatigue.2020.106111
Quantitative APT analysis of solid transmutants in ferritic-martensitic steels after irradiation in SINQ targets: experimental validation of neutronic calculations
Cui, L., Li, J., Gerstl, S., Pouchon, M., & Dai, Y. (2021). Quantitative APT analysis of solid transmutants in ferritic-martensitic steels after irradiation in SINQ targets: experimental validation of neutronic calculations. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 502, 1-9. https://doi.org/10.1016/j.nimb.2021.05.017
Post-irradiation examinations of SINQ Target-11
Dai, Y., Boutellier, V., Grabherr, R., Urech, A., Blau, B., Welte, J., … Wohlmuther, M. (2021). Post-irradiation examinations of SINQ Target-11. In K. Kikuchi (Ed.), Materials science forum: Vol. 1024. Spallation materials technology (pp. 41-52). https://doi.org/10.4028/www.scientific.net/MSF.1024.41
Statistical inference and performance evaluation for failure assessment models of pipeline with external axial surface cracks
Guo, L., Niffenegger, M., & Jing, Z. (2021). Statistical inference and performance evaluation for failure assessment models of pipeline with external axial surface cracks. International Journal of Pressure Vessels and Piping, 194, 104480 (20 pp.). https://doi.org/10.1016/j.ijpvp.2021.104480
The speciation of niobium in the oxide layer of an irradiated Low-Tin ZIRLO nuclear material
Hawes, J., Warnicke, P., Burr, P., Ferreira Sanchez, D., Grolimund, D., Partezana, J., … Abolhassani, S. (2021). The speciation of niobium in the oxide layer of an irradiated Low-Tin ZIRLO nuclear material. Corrosion Science, 190, 109630 (12 pp.). https://doi.org/10.1016/j.corsci.2021.109630
Reactivity worth measurement of the lead target on VENUS-II light water reactor and validation of evaluated nuclear data
Jiang, W., Gu, L., Zhu, Q. F., Zhou, Q., Ma, F., Zhang, L., … Chen, L. (2021). Reactivity worth measurement of the lead target on VENUS-II light water reactor and validation of evaluated nuclear data. Annals of Nuclear Energy, 154, 108106 (8 pp.). https://doi.org/10.1016/j.anucene.2020.108106
Neutron radiography for local modelling of thermochemical heat storage reactors: case study on SrCl<sub>2</sub>-NH<sub>3</sub>
Karabanova, A., Berdiyeva, P., Helfen, L., Tengattini, A., Bücherl, T., Makowska, M. G., … Blanchard, D. (2021). Neutron radiography for local modelling of thermochemical heat storage reactors: case study on SrCl2-NH3. International Journal of Heat and Mass Transfer, 178, 121287 (11 pp.). https://doi.org/10.1016/j.ijheatmasstransfer.2021.121287
High temperature corrosion evaluation and lifetime prediction of porous Fe22Cr stainless steel in air in temperature range 700-900°C
Koszelow, D., Makowska, M., Marone, F., Karczewski, J., Jasiński, P., & Molin, S. (2021). High temperature corrosion evaluation and lifetime prediction of porous Fe22Cr stainless steel in air in temperature range 700-900°C. Corrosion Science, 189, 109589 (11 pp.). https://doi.org/10.1016/j.corsci.2021.109589
NEURAP - a dedicated neutron-imaging facility for highly radioactive samples
Lehmann, E., Thomsen, K., Strobl, M., Trtik, P., Bertsch, J., & Dai, Y. (2021). NEURAP - a dedicated neutron-imaging facility for highly radioactive samples. Journal of Imaging, 7(3), 57 (14 pp.). https://doi.org/10.3390/jimaging7030057
Genetic algorithm based temperature control of the dense granular spallation target in China initiative accelerator driven system
Li, J. Y., Dai, Y., Gu, L., Zhang, Y. P., He, Z. Y., Xu, H. S., … Wang, D. W. (2021). Genetic algorithm based temperature control of the dense granular spallation target in China initiative accelerator driven system. Annals of Nuclear Energy, 154, 108127 (8 pp.). https://doi.org/10.1016/j.anucene.2021.108127
Neutronics analysis of thorium-uranium based molten salt blanket in stellarator-type FFHR
Li, J. Y., Gu, L., Xu, H. S., Zhang, Y. P., Dai, Y., Yao, C. F., … Jiang, W. (2021). Neutronics analysis of thorium-uranium based molten salt blanket in stellarator-type FFHR. Fusion Engineering and Design, 162, 112098 (8 pp.). https://doi.org/10.1016/j.fusengdes.2020.112098
The PyNE-based burnup analysis method for accelerator-driven subcritical systems
Li, J. Y., Gu, L., Xu, H. S., Dai, Y., Zhang, Y. P., Yao, C. F., … Yang, S. (2021). The PyNE-based burnup analysis method for accelerator-driven subcritical systems. Nuclear Technology, 207(2), 270-284. https://doi.org/10.1080/00295450.2020.1757963
Investigation on optimization of self-adaptive closure law for load rejection to a reversible pump turbine based on CFD
Mao, X., Chen, D., Wang, Y., Mao, G., & Zheng, Y. (2021). Investigation on optimization of self-adaptive closure law for load rejection to a reversible pump turbine based on CFD. Journal of Cleaner Production, 283, 124739 (15 pp.). https://doi.org/10.1016/j.jclepro.2020.124739
Neural network-based prediction for surface characteristics in CO<sub>2</sub> laser micro-milling of glass fiber reinforced plastic composite
Prakash, S., & Suman, S. (2021). Neural network-based prediction for surface characteristics in CO2 laser micro-milling of glass fiber reinforced plastic composite. Neural Computing & Applications, 33, 11517-11529. https://doi.org/10.1007/s00521-021-05818-w
Study on hydrogen embrittlement and dynamic strain ageing on low-alloy reactor pressure vessel steels
Rao, G. S., Yagodzinskyy, Y., Que, Z., Spätig, P., & Seifert, H. P. (2021). Study on hydrogen embrittlement and dynamic strain ageing on low-alloy reactor pressure vessel steels. Journal of Nuclear Materials, 556, 153161 (13 pp.). https://doi.org/10.1016/j.jnucmat.2021.153161
Results of an international round-robin exercise on electrochemical impedance spectroscopy
Ritter, S., Bosch, R. W., Huet, F., Ngo, K., Cottis, R. A., Bakalli, M., … Zhang, W. (2021). Results of an international round-robin exercise on electrochemical impedance spectroscopy. Corrosion Engineering Science and Technology, 56(3), 254-268. https://doi.org/10.1080/1478422X.2020.1850070
Materials and corrosion issues in the primary coolant circuit of boiling water reactors
Seifert, H. P., & Bertsch, J. (2021). Materials and corrosion issues in the primary coolant circuit of boiling water reactors. Techniques de l'ingénieur, EBN 3 762 (30 pp.).
 

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