Erwin Alhassan
Erwin Alhassan
Belgian Nuclear Research Institute (SCK-CEN)
Verified email at sckcen.be
Title
Cited by
Cited by
Year
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
302014
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
272016
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
252015
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
222014
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
152017
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
152014
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
142010
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
122011
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
102011
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
82016
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
82014
Selecting benchmarks for reactor calculations.
E Alhassan, H Sjöstrand, J Duan, P Helgesson, S Pomp, M Osterlund, ...
82014
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
82013
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
72015
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
72014
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
72013
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
62020
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
52014
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