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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
Non-destructive testing of the MEGAPIE target
Dai, Y., Wohlmuther, M., Boutellier, V., Hahl, S., Lagotzki, A., Leu, H., … Wagner, W. (2016). Non-destructive testing of the MEGAPIE target. Journal of Nuclear Materials, 468, 221-227. https://doi.org/10.1016/j.jnucmat.2015.08.026
Influence of Pt deposition on the behaviour of zircaloy cladding under boiling conditions in simulated BWR environment 
Grundler, P. V., Ritter, S., Veleva, L., Wiese, H., Oliver, L., Helmerson, B., … Ledergerber, G. (2016). Influence of Pt deposition on the behaviour of zircaloy cladding under boiling conditions in simulated BWR environment . In Vol. 1. 20th international conference on water chemistry of nuclear reactor systems (NPC 2016) (p. 30 (12 pp.). Nuclear Institute, CK International House.
Distribution and surface enrichment of radionuclides in lead-bismuth eutectic from spallation targets
Hammer-Rotzler, B., Neuhausen, J., Boutellier, V., Wohlmuther, M., Zanini, L., David, J. C., … Schumann, D. (2016). Distribution and surface enrichment of radionuclides in lead-bismuth eutectic from spallation targets. European Physical Journal Plus, 131(7), 233 (18 pp.). https://doi.org/10.1140/epjp/i2016-16233-1
Corrosion and hydrogen uptake in zirconium claddings irradiated in light water reactors
Abolhassani, S., Bart, G., Bertsch, J., Grosse, M., Hallstadius, L., Hermann, A., … Wiese, H. (2015). Corrosion and hydrogen uptake in zirconium claddings irradiated in light water reactors. In R. J. Comstock & P. Barbéris (Eds.), Vol. STP1543. Zirconium in the nuclear industry. 17th international symposium (pp. 540-573). https://doi.org/10.1520/STP154320130007
Radiochemical determination of rare earth elements in proton-irradiated lead-bismuth eutectic
Hammer, B., Neuhausen, J., Boutellier, V., Wohlmuther, M., Türler, A., & Schumann, D. (2015). Radiochemical determination of rare earth elements in proton-irradiated lead-bismuth eutectic. Analytical Chemistry, 87(11), 5656-5663. https://doi.org/10.1021/acs.analchem.5b00955
Radiochemical determination of <sup>129</sup>I and <sup>36</sup>Cl in MEGAPIE, a proton irradiated lead-bismuth eutectic spallation target
Hammer-Rotzler, B., Neuhausen, J., Vockenhuber, C., Boutellier, V., Wohlmuther, M., Türler, A., & Schumann, D. (2015). Radiochemical determination of 129I and 36Cl in MEGAPIE, a proton irradiated lead-bismuth eutectic spallation target. Radiochimica Acta, 103(11), 745-758. https://doi.org/10.1515/ract-2015-2420
Analysis of the <sup>207</sup>Bi, <sup>194</sup>Hg/Au and <sup>173</sup>Lu distribution in the irradiated MEGAPIE target
Hammer, B., Neuhausen, J., Boutellier, V., Linder, H. P., Shcherbina, N., Wohlmuther, M., … Schumann, D. (2014). Analysis of the 207Bi, 194Hg/Au and 173Lu distribution in the irradiated MEGAPIE target. Journal of Nuclear Materials, 450(1-3), 278-286. https://doi.org/10.1016/j.jnucmat.2013.09.016
FeCrAlY and TiN coatings on T91 steel after irradiation with 72 MeV protons in flowing LBE
Dai, Y., Boutellier, V., Gavillet, D., Glasbrenner, H., Weisenburger, A., & Wagner, W. (2012). FeCrAlY and TiN coatings on T91 steel after irradiation with 72 MeV protons in flowing LBE. Journal of Nuclear Materials, 431(1-3), 66-76. https://doi.org/10.1016/j.jnucmat.2011.11.006
The fourth SINQ Target Irradiation Program, STIP-IV
Dai, Y., Brun, R., Gao, W., Geissmann, K., Hahl, S., Hou, H., … Zanini, L. (2012). The fourth SINQ Target Irradiation Program, STIP-IV. Journal of Nuclear Materials, 431(1-3), 2-9. https://doi.org/10.1016/j.jnucmat.2011.11.004
Post-irradiation analysis of the tantalum container of an ISOLDE LBE target
Noah, E., Boutellier, V., Brütsch, R., Catherall, R., Gavillet, D., Krbanjevic, J., … Zanini, L. (2012). Post-irradiation analysis of the tantalum container of an ISOLDE LBE target. Journal of Nuclear Materials, 431(1-3), 60-65. https://doi.org/10.1016/j.jnucmat.2011.11.034
Pre-calculation using the Falcon fuel behaviour code of the fuel rod design parameters and the test-conditions for a two-run Halden LOCA test with KKL BWR high-burnup fuel
Khvostov, G., Kolstad, E., Ledergerber, G., Zimmermann, M. A., Wiesenack, W., Brémond, O., … Martin, M. (2011). Pre-calculation using the Falcon fuel behaviour code of the fuel rod design parameters and the test-conditions for a two-run Halden LOCA test with KKL BWR high-burnup fuel. In Vol. HPR-374. Enlarged Halden programme group meeting. Proceedings of the fuel & materials sessions (p. F2.7 (21 pp.). Institutt for Energiteknikk.