Erwin Alhassan

发表

Incorporating Experimental Information in the Total Monte Carlo Methodology Using File Weights

Petter Helgesson, Henrik Sjöstrand, Arjan J. Koning, 2015 .

Nuclear Data Uncertainty Quantification for the Nuclear Fuel Cycle Using the TMC Method

Petter Helgesson, Henrik Sjöstrand, Erwin Alhassan, 2015 .

Towards Transparent, Reproducible And Justified Nuclear Data Uncertainty Propagation For Lwr Applications

Petter Helgesson, Henrik Sjöstrand, Arjan J. Koning, 2015 .

Development Of Drag-MOC : A tool for the study of uncertainty analysis through the deterministic OpenMOC transport code

Petter Helgesson, Henrik Sjöstrand, Erwin Alhassan, 2016 .

DRAG-MOC: A tool for the study of uncertainty analysis through OpenMOC

Petter Helgesson, Henrik Sjöstrand, Erwin Alhassan, 2015 .

Stability analysis of the Ghana Research Reactor-1 (GHARR-1)

Erwin Alhassan, Benjamin J.B. Nyarko, Ehk Akaho, 2013 .

Determination of thermal hydraulic data of GHARR-1 under reactivity insertion transients using the PARET/ANL code

Erwin Alhassan, E.H.K. Akaho, Benjamin J.B. Nyarko, 2011 .

Including experimental information in TMC using file weights from automatically generated experimental covariance matrices

Petter Helgesson, Henrik Sjöstrand, Arjan J. Koning, 2015 .

On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology

Petter Helgesson, Henrik Sjöstrand, Erwin Alhassan, 2016 .

Nuclear data uncertainty propagation for a lead-cooled fast reactor: Combining TMC with criticality benchmarks for improved accuracy

Erwin Alhassan, E. Alhassan, 2014 .

Selecting benchmarks for reactor calculations.

Petter Helgesson, Henrik Sjöstrand, Arjan J. Koning, 2014 .

Selecting benchmarks for reactor simulations: An application to a lead fast reactor

Petter Helgesson, Henrik Sjöstrand, Erwin Alhassan, 2016 .

UO2 versus MOX: Propagated Nuclear Data Uncertainty for keff, with Burnup

Petter Helgesson, Henrik Sjöstrand, Arjan J. Koning, 2014 .

Uncertainty analysis of Lead cross sections on reactor safety for ELECTRA

Henrik Sjöstrand, Arjan J. Koning, Dimitri Rochman, 2014, ICS 2014.

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

Petter Helgesson, Henrik Sjöstrand, Arjan J. Koning, 2015 .

Combining Total Monte Carlo and Benchmarks for Nuclear Data Uncertainty Propagation on a Lead Fast Reactor's Safety Parameters

Henrik Sjöstrand, Arjan J. Koning, Dimitri Rochman, 2014 .

Combining Total Monte Carlo and Unified Monte Carlo : Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances

Petter Helgesson, Henrik Sjöstrand, Arjan J. Koning, 2017 .

Uncertainty and correlation analysis of lead nuclear data on reactor parameters for the European Lead Cooled Training Reactor

Petter Helgesson, Henrik Sjöstrand, Arjan J. Koning, 2015 .