| FreeCAD based Monte Carlo modeling approach for fusion reactor facilities
Li, J. Y., Gu, L., Xu, H. S., Dai, Y., Zhang, Y. P., Yu, R., … Jiang, W. (2020). FreeCAD based Monte Carlo modeling approach for fusion reactor facilities. Fusion Engineering and Design, 155, 111711 (10 pp.). https://doi.org/10.1016/j.fusengdes.2020.111711 |
| A comprehensive theoretical assessment of potential 'tramp uranium' isotopic evolution in BWR reactors
Vasiliev, A., Grimm, P., Ferroukhi, H., Pecchia, M., & Ledergerber, G. (2020). A comprehensive theoretical assessment of potential 'tramp uranium' isotopic evolution in BWR reactors. Annals of Nuclear Energy, 144, 107489 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107489 |
| Positron annihilation spectroscopy studies of irradiated Fe-based alloys using different radioisotope sources
Krsjak, V., Degmova, J., Lauko, R., Snopek, J., Saro, M., Sedlackova, K., … Slugen, V. (2018). Positron annihilation spectroscopy studies of irradiated Fe-based alloys using different radioisotope sources. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 434, 73-80. https://doi.org/10.1016/j.nimb.2018.08.031 |
| Comparison of different target material options for the European Spallation Source based on certain aspects related to the final disposal
Kókai, Z., Török, S., Zagyvai, P., Kiselev, D., Moormann, R., Börcsök, E., … Janik, J. (2018). Comparison of different target material options for the European Spallation Source based on certain aspects related to the final disposal. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 416, 1-8. https://doi.org/10.1016/j.nimb.2017.11.027 |
| Localized neutron flux assessment and verification studies using MCNPX PWR full core model
Vasiliev, A., Ferroukhi, H., Pecchia, M., & Pautz, A. (2016). Localized neutron flux assessment and verification studies using MCNPX PWR full core model. Annals of Nuclear Energy, 92, 317-332. https://doi.org/10.1016/j.anucene.2016.01.026 |
| Interfacing MCNPX and McStas for simulation of neutron transport
Klinkby, E., Lauritzen, B., Nonbøl, E., Kjær Willendrup, P., Filges, U., Wohlmuther, M., & Gallmeier, F. X. (2013). Interfacing MCNPX and McStas for simulation of neutron transport. Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 700, 106-110. https://doi.org/10.1016/j.nima.2012.10.052 |
| Gamma-ray spectrometric measurements of fission rate ratios between fresh and burnt fuel following irradiation in a zero-power reactor
Kröhnert, H., Perret, G., Murphy, M. F., & Chawla, R. (2013). Gamma-ray spectrometric measurements of fission rate ratios between fresh and burnt fuel following irradiation in a zero-power reactor. Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 698, 72-80. https://doi.org/10.1016/j.nima.2012.09.008 |
| Bi-spectral moderator for spallation sources optimized for instrument requirements
Reiss, T., Filges, U., Gallmeier, F., Talanov, V., & Wohlmuther, M. (2013). Bi-spectral moderator for spallation sources optimized for instrument requirements. Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 728, 117-125. https://doi.org/10.1016/j.nima.2013.06.093 |
| Analysis of pin removal experiments conducted in an SCWR-like test lattice
Chawla, R., Rätz, D., Jordan, K. A., & Perret, G. (2012). Analysis of pin removal experiments conducted in an SCWR-like test lattice. In Vol. 4. PHYSOR 2012: advances in reactor physics (pp. 3565-3578). |
| A novel design approach for a neutron measurement station for burnt fuel
Dietler, R., Hursin, M., Perret, G., Jordan, K., & Chawla, R. (2012). A novel design approach for a neutron measurement station for burnt fuel. Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 693, 59-66. https://doi.org/10.1016/j.nima.2012.07.009 |
| Towards a reference numerical scheme using MCNPX for PWR control rod tip fluence estimations
Ferroukhi, H., Vasiliev, A., Dufresne, A., & Chawla, R. (2012). Towards a reference numerical scheme using MCNPX for PWR control rod tip fluence estimations. In Vol. 1. PHYSOR 2012: advances in reactor physics (pp. 401-417). |
| Towards the reanalysis of void coefficients measurements at PROTEUS for High Conversion Light Water Reactor lattices
Hursin, M., Koeberl, O., & Perret, G. (2012). Towards the reanalysis of void coefficients measurements at PROTEUS for High Conversion Light Water Reactor lattices. In Vol. 3. PHYSOR 2012: advances in reactor physics (pp. 2558-2568). |
| Analysis of the BN-600 fast-spectrum core mock-up at BFS-2 zero-power facility using MCNPX
Marinoni, A., Girardin, G., & Mikityuk, K. (2012). Analysis of the BN-600 fast-spectrum core mock-up at BFS-2 zero-power facility using MCNPX. Annals of Nuclear Energy, 44, 26-33. https://doi.org/10.1016/j.anucene.2012.01.011 |
| Characteristics of the neutron irradiation facilities of the PSI Calibration Laboratory
Hoedlmoser, H., Schuler, C., Butterweck, G., & Mayer, S. (2011). Characteristics of the neutron irradiation facilities of the PSI Calibration Laboratory. In M. E. Hamm & R. W. Hamm (Eds.), AIP conference proceedings: Vol. 1412. Applications of nuclear techniques. Eleventh international conference (pp. 385-392). https://doi.org/10.1063/1.3665339 |
| Refined Monte Carlo analysis of the H.B. Robinson-2 reactor pressure vessel dosimetry benchmark
Pittarello, R., Vasiliev, A., Ferroukhi, H., & Chawla, R. (2011). Refined Monte Carlo analysis of the H.B. Robinson-2 reactor pressure vessel dosimetry benchmark. Annals of Nuclear Energy, 38(9), 1842-1851. https://doi.org/10.1016/j.anucene.2011.05.017 |
| Experimental validation of control rod related perturbations of moderator regions in an SCWR-like fuel lattice
Rätz, D., Jordan, K. A., Perret, G., & Chawla, R. (2011). Experimental validation of control rod related perturbations of moderator regions in an SCWR-like fuel lattice. Annals of Nuclear Energy, 38(11), 2319-2332. https://doi.org/10.1016/j.anucene.2011.07.007 |
| Comparison of neutron data libraries for the analysis of the "H. B. ROBINSON-2 Pressure Vessel Benchmark" with the MCNPX code
Vasiliev, A., Kolbe, E., Ferroukhi, H., & Pittarello, R. (2011). Comparison of neutron data libraries for the analysis of the "H. B. ROBINSON-2 Pressure Vessel Benchmark" with the MCNPX code. Journal of the Korean Physical Society, 59(23), 2047-2050. https://doi.org/10.3938/jkps.59.2047 |
| Simulating the angular response of Makrofol as a detector for neutron induced recoils
Zhang, G., Becker, F., Urban, M., Xuan, Y., Fürstner, M., & Mayer, S. (2011). Simulating the angular response of Makrofol as a detector for neutron induced recoils. Radiation Measurements, 46(4), 405-408. https://doi.org/10.1016/j.radmeas.2011.01.020 |
| Freshly induced short-lived gamma-ray activity as a measure of fission rates in lightly re-irradiated spent fuel
Kröhnert, H., Perret, G., Murphy, M. F., & Chawla, R. (2010). Freshly induced short-lived gamma-ray activity as a measure of fission rates in lightly re-irradiated spent fuel. Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 624(1), 101-108. https://doi.org/10.1016/j.nima.2010.09.033 |
| Performance of a Monte-Carlo solution for the H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark
Vasiliev, A., Ferroukhi, H., & Kolbe, E. (2010). Performance of a Monte-Carlo solution for the H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark. Annals of Nuclear Energy, 37(10), 1404-1410. https://doi.org/10.1016/j.anucene.2010.05.019 |
