| UO2 versus MOX: Propagated Nuclear Data Uncertainty for keff, with Burnup P Helgesson, D Rochman, H Sjöstrand, E Alhassan, A Koning Nuclear Science and Engineering 177 (3), 321-336, 2014 | 30 | 2014 |
| On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology E Alhassan, H Sjöstrand, P Helgesson, M Österlund, S Pomp, AJ Koning, ... Progress in Nuclear Energy 88, 43-52, 2016 | 27 | 2016 |
| Uncertainty and correlation analysis of lead nuclear data on reactor parameters for the European Lead Cooled Training Reactor E Alhassan, H Sjöstrand, P Helgesson, JK Arjan, M Österlund, S Pomp, ... Annals of Nuclear Energy 75, 26 – 37, 2015 | 25 | 2015 |
| Propagation of nuclear data uncertainties for ELECTRA burn-up calculations H Sjöstrand, E Alhassan, J Duan, C Gustavsson, AJ Koning, S Pomp, ... Nuclear Data Sheets 118, 527-530, 2014 | 22 | 2014 |
| Combining Total Monte Carlo and benchmarks for nuclear data uncertainty propagation on a lead fast reactor's safety parameters E Alhassan, H Sjöstrand, J Duan, C Gustavsson, AJ Koning, S Pomp, ... Nuclear Data Sheets 118, 542-544, 2014 | 18* | 2014 |
| Incorporating experimental information in the TMC methodology using file weights P Helgesson, H Sjöstrand, A Koning, D Rochman, E Alhassan, S Pomp | 18* | 2014 |
| Combining total Monte Carlo and Unified Monte Carlo: Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances P Helgesson, H Sjöstrand, AJ Koning, J Rydén, D Rochman, E Alhassan, ... Progress in Nuclear Energy 96, 76-96, 2017 | 15 | 2017 |
| Total Monte Carlo evaluation for dose calculations H Sjöstrand, E Alhassan, S Conroy, J Duan, C Hellesen, S Pomp, ... Radiation protection dosimetry 161 (1-4), 312-315, 2014 | 15 | 2014 |
| Analysis of reactivity temperature coefficient for light water moderated HEU-UAl4 and LEU-UO2 lattices of MNSR E Alhassan, EHK Akaho, BJB Nyarko, NA Adoo, VY Agbodemegbe, ... Journal Applied Science Research 6 (9), 1431-1439, 2010 | 14 | 2010 |
| Determination of thermal hydraulic data of GHARR-1 under reactivity insertion transients using the PARET/ANL code NA Adoo, BJB Nyarko, EHK Akaho, E Alhassan, VY Agbodemegbe, ... Nuclear engineering and design 241 (12), 5203-5210, 2011 | 12 | 2011 |
| Determination of trace elements in Ghanaian shea butter and shea nut by neutron activation analysis (NAA) E Alhassan, SE Agbemava, NA Adoo, VY Agbodemegbe, CY Bansah, ... Research Journal of Applied Sciences, Engineering and Technology 3 (1), 22-25, 2011 | 10 | 2011 |
| Selecting benchmarks for reactor simulations: An application to a lead fast reactor E Alhassan, H Sjöstrand, P Helgesson, M Österlund, S Pomp, AJ Koning, ... Annals of Nuclear Energy 96, 158-169, 2016 | 8 | 2016 |
| Uncertainty study of nuclear model parameters for the n+ 56Fe reactions in the fast neutron region below 20 MeV J Duan, S Pomp, H Sjöstrand, E Alhassan, C Gustavsson, M Österlund, ... Nuclear Data Sheets 118, 346-348, 2014 | 8 | 2014 |
| Selecting benchmarks for reactor calculations. E Alhassan, H Sjöstrand, J Duan, P Helgesson, S Pomp, M Osterlund, ... | 8 | 2014 |
| Stability analysis of the Ghana Research Reactor-1 (GHARR-1) R Della, E Alhassan, NA Adoo, CY Bansah, EHK Akaho, BJB Nyarko Energy Conversion and Management 74, 587–593, 2013 | 8 | 2013 |
| Experiments and theoretical data for studying the impact of fission yield uncertainties on the nuclear fuel cycle with TALYS/GEF and the Total Monte Carlo method S Pomp, A Al-Adili, E Alhassan, C Gustavsson, P Helgesson, C Hellesen, ... Nuclear Data Sheets 123, 220-224, 2015 | 7 | 2015 |
| Uncertainty analysis of Lead cross sections on reactor safety for ELECTRA E Alhassan, H Sjöstrand, J Duan, C Gustavsson, S Pomp, M Österlund, ... SNA+ MC 2013-Joint International Conference on Supercomputing in Nuclear …, 2014 | 7 | 2014 |
| Assessing the Effect of Fuel Burnup on Control Rod Worth for HEU and LEU Cores of Gharr-1 EK Boafo, E Alhassan, EHK Akaho, C Odoi Research Journal of Applied Sciences, Engineering and Technology 5 (4), 1129 …, 2013 | 7 | 2013 |
| Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo E Alhassan, D Rochman, H Sjöstrand, A Vasiliev, AJ Koning, H Ferroukhi Annals of Nuclear Energy 139, 107239, 2020 | 6 | 2020 |
| Utilizing the burnup capability in MCNPX to perform depletion analysis of an MNSR fuel EK Boafo, E Alhassan, EHK Akaho Annals of Nuclear Energy 73, 478-483, 2014 | 5 | 2014 |
Henrik SjöstrandUppsala universityVerified email at physics.uu.se
