1. Alhassan, E., 2015. Nuclear data uncertainty quantification and data assimilation for a lead-cooled fast reactor: Using integral experiments for improved accuracy, Digital Comprehensive Summaries of Uppsala Dissertations from the Faculty of Science and Technology 1315. 85 pp. Uppsala University: Acta Universitatis Upsaliensis (2015). ISBN 978-91-554-9407-0.
2. Combining Total Monte Carlo and benchmarks for nuclear data uncertainty propagation on a lead fast reactor’s safety parameters;Alhassan;Nucl. Data Sheets,2014
3. Selecting benchmarks for reactor calculations;Alhassan,2014
4. Uncertainty and correlation analysis of lead nuclear data on reactor parameters for the European Lead Cooled Training reactor;Alhassan;Ann. Nucl. Energy,2015
5. Alhassan, E., Rochman, D., Helgesson, P., Sjöstrand, H., Hernández-Solís, A., Koning, A.J., Pomp, S., 2016a. Combining differential and integral experimental data for cross section adjustment in the fast neutron energy region using TMC, in preparation.