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The metamorphic footprint of western Laurentia preserved in subducted rocks from southern Australia
Brown, D. A., Morrissey, L. J., Hand, M., Mulder, J. A., Wade, B., & Barrote, V. (2024). The metamorphic footprint of western Laurentia preserved in subducted rocks from southern Australia. Journal of Metamorphic Geology. https://doi.org/10.1111/jmg.12770
Duplex and optimized ZIRLO<sup>TM</sup> fuel cladding experience in a European high-duty pressurized water reactor
Helmersson, B., Holmkvist, C., Girardin, G., Wiese, H., Martin, M., Anghel, C., … Oldberg, K. (2023). Duplex and optimized ZIRLOTM fuel cladding experience in a European high-duty pressurized water reactor. In ASTM special technical publication: Vol. STP 1645. International symposium on zirconium in the nuclear industry (pp. 599-614). https://doi.org/10.1520/STP164520220080
Insights into the interfacial speciation of Ni in the corrosion layer of high burnup Zircaloy-2 cladding: a combined XRD, XAS, and LFDFT study
Kuri, G., Ramanantoanina, H., Bhattacharya, S., Bertsch, J., & Martin, M. (2023). Insights into the interfacial speciation of Ni in the corrosion layer of high burnup Zircaloy-2 cladding: a combined XRD, XAS, and LFDFT study. Corrosion Science, 215, 111024 (13 pp.). https://doi.org/10.1016/j.corsci.2023.111024
Atomic-scale insights into structural distortions in irradiated UO<sub>2</sub> at an intermediate burnup around 50 MWd/kgU
Bhattacharya, S., Kuri, G., Martin, M., Bertsch, J., & Pouchon, M. A. (2022). Atomic-scale insights into structural distortions in irradiated UO2 at an intermediate burnup around 50 MWd/kgU. In Proceedings of TopFuel 2022 light water reactor fuel performance conference (pp. 278-285). https://doi.org/10.13182/TopFuel22-38929
Recent examinations of hydride orientation for zircaloy-2 RXA fuel rods with doped and un-doped pellets
Helmersson, B., Schrire, D., Kucuk, A., Blair, P., Anghel, C., Martin, M., … Hallman, L. (2022). Recent examinations of hydride orientation for zircaloy-2 RXA fuel rods with doped and un-doped pellets. In Proceedings of TopFuel 2022 light water reactor fuel performance conference (pp. 495-504). https://doi.org/10.13182/TopFuel22-38926
Towards an improved understanding of the mechanisms involved in the increased hydrogen uptake and corrosion at high burnups in zirconium based claddings
Abolhassani, S., Baris, A., Grabherr, R., Hawes, J., Colldeweih, A., Vanta, R., … Limbäck, M. (2021). Towards an improved understanding of the mechanisms involved in the increased hydrogen uptake and corrosion at high burnups in zirconium based claddings. In A. T. Motta & S. K. Yagnik (Eds.), ASTM International: selected technical papers: Vol. STP1622. Zirconium in the nuclear industry: 19th international symposium (pp. 435-466). https://doi.org/10.1520/STP162220190052
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
Framatome's evolutionary ATF solution: feedback from the irradiation programs on PROtect's Cr-coated M5<sub>Framatome</sub> cladding
Duquesne, L., Bischoff, J., Buchanan, K., Schweitzer, E., Nimishakavi, K., Girardin, G., … Pouchon, M. (2021). Framatome's evolutionary ATF solution: feedback from the irradiation programs on PROtect's Cr-coated M5Framatome cladding. In TopFuel2021 (p. (10 pp.). European Nuclear Society.
Radiological characterisation in view of nuclear reactor decommissioning: on-site benchmarking exercise of a biological shield
Herranz, M., Boden, S., Völgyesi, P., Idoeta, R., Broeckx, W., Ruiz González, J., … Legarda, F. (2021). Radiological characterisation in view of nuclear reactor decommissioning: on-site benchmarking exercise of a biological shield. Progress in Nuclear Energy, 137, 103740 (13 pp.). https://doi.org/10.1016/j.pnucene.2021.103740
&lt;sup&gt;243&lt;/sup&gt;Am certified reference material for mass spectrometry
Jakopič, R., Fankhauser, A., Aregbe, Y., Richter, S., Crozet, M., Maillard, C., … Pommé, S. (2021). 243Am certified reference material for mass spectrometry. Journal of Radioanalytical and Nuclear Chemistry, 327(1), 495-504. https://doi.org/10.1007/s10967-020-07521-x
Modeling of sphere-pac fuel
Pouchon, M. A., Nordström, L. Å., & Hellwig, C. (2021). Modeling of sphere-pac fuel. In R. J. M. Konings & R. E. Stoller (Eds.), Vol. 5. Comprehensive nuclear materials (pp. 436-463). https://doi.org/10.1016/B978-0-08-102865-0.00068-6
Production of mass-separated erbium-169 towards the first preclinical <em>in vitro</em> investigations
Talip, Z., Borgna, F., Müller, C., Ulrich, J., Duchemin, C., Ramos, J. P., … van der Meulen, N. P. (2021). Production of mass-separated erbium-169 towards the first preclinical in vitro investigations. Frontiers in Medicine, 8, 643175 (11 pp.). https://doi.org/10.3389/fmed.2021.643175
Separation and recovery of exotic radiolanthanides from irradiated tantalum targets for half-life measurements
Chiera, N. M., Talip, Z., Fankhauser, A., & Schumann, D. (2020). Separation and recovery of exotic radiolanthanides from irradiated tantalum targets for half-life measurements. PLoS One, 15(7), e0235711 (19 pp.). https://doi.org/10.1371/journal.pone.0235711
Suppression of the &lt;em&gt;s&lt;/em&gt;-wave order parameter near the surface of the infinite-layer electron-doped cuprate superconductor Sr&lt;sub&gt;0.9&lt;/sub&gt;La&lt;sub&gt;0.1&lt;/sub&gt;CuO&lt;sub&gt;2&lt;/sub&gt;
Khasanov, R., Shengelaya, A., Brütsch, R., & Keller, H. (2020). Suppression of the s-wave order parameter near the surface of the infinite-layer electron-doped cuprate superconductor Sr0.9La0.1CuO2. Condensed Matter, 5(3), 50 (11 pp.). https://doi.org/10.3390/condmat5030050
Selective Cs-removal from highly acidic spent nuclear fuel solutions
Lin, M., Kajan, I., Schumann, D., Türler, A., & Fankhauser, A. (2020). Selective Cs-removal from highly acidic spent nuclear fuel solutions. Radiochimica Acta, 108(8), 615-626. https://doi.org/10.1515/ract-2019-3187
Sample container for high-resolution neutron imaging of spent nuclear fuel cladding sections
Trtik, P., Zubler, R., Gong, W., Grabherr, R., Bertsch, J., & Duarte, L. I. (2020). Sample container for high-resolution neutron imaging of spent nuclear fuel cladding sections. Review of Scientific Instruments, 91(5), 056103 (3 pp.). https://doi.org/10.1063/1.5143226
Contribution of an interlaboratory comparison to the certification of the STAM/IRMM-0243 &lt;sup&gt;243&lt;/sup&gt;Am reference material
Crozet, M., Roudil, D., Maillard, C., Rivier, C., Jakopič, R., Fankhauser, A., … Richter, S. (2019). Contribution of an interlaboratory comparison to the certification of the STAM/IRMM-0243 243Am reference material. Journal of Radioanalytical and Nuclear Chemistry, 319(3), 717-725. https://doi.org/10.1007/s10967-018-06404-6
SCC mitigation in boiling water reactors: platinum deposition and durability on structural materials
Grundler, P. V., Ritter, S., & Veleva, L. (2019). SCC mitigation in boiling water reactors: platinum deposition and durability on structural materials. In J. H. Jackson, D. Paraventi, & M. Wright (Eds.), The minerals, metals & materials series: Vol. 2. Proceedings of the 18th international conference on environmental degradation of materials in nuclear power systems – water reactors (pp. 1685-1700). https://doi.org/10.1007/978-3-030-04639-2_113
Study of electronic structure in the L-edge spectroscopy of actinide materials: UO&lt;sub&gt;2&lt;/sub&gt; as an example
Ramanantoanina, H., Kuri, G., Martin, M., & Bertsch, J. (2019). Study of electronic structure in the L-edge spectroscopy of actinide materials: UO2 as an example. Physical Chemistry Chemical Physics, 21(15), 7789-7801. https://doi.org/10.1039/c9cp01021a
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.), ASTM special technical publication: Vol. STP1597. Zirconium in the nuclear industry: 18th international symposium (pp. 614-644). https://doi.org/10.1520/STP159720160039
 

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