G. Eynde

发表

Nuclear data sensitivity and uncertainty analysis of effective neutron multiplication factor in various MYRRHA core configurations

J. Heyse, Ó. Cabellos, P. Schillebeeckx, 2017 .

Development of a core management tool for MYRRHA

Stefan Vandewalle, Gert Van den Eynde, David Jalůvka, 2013 .

Nuclear data uncertainty propagation to integral responses using SANDY

G. Van den Eynde, Pierre-Etienne Labeau, Luca Fiorito, 2017 .

Nuclear data sensitivity/uncertainty analysis for XT-ADS

T. Sugawara, G. V. D. Eynde, A. Stankovskiy, 2011 .

An easy to implement global variance reduction procedure for MCNP

G. Van den Eynde, J. E. Hoogenboom, J. Hoogenboom, 2011 .

Development of time-dependent reaction rates to optimise predictor–corrector algorithm in ALEPH burn-up code

P. Labeau, G. V. D. Eynde, L. Fiorito, 2013 .

Calculating near-singular eigenvalues of the neutron transport operator with arbitrary order anisotropic scattering

Robert Beauwens, Ernest Mund, Gert Van den Eynde, 2010, Math. Comput. Simul..

Neutron transport with anisotropic scattering: theory and applications

R. Beauwens, G. V. D. Eynde, G. Eynde, 2005 .

Partitioning and transmutation contribution of MYRRHA to an EU strategy for HLW management and main achievements of MYRRHA related FP7 and H2020 projects: MYRTE, MARISA, MAXSIMA, SEARCH, MAX, FREYA, ARCAS

J. Biarrotte, H. Abderrahim, P. Baeten, 2020, EPJ Nuclear Sciences & Technologies.

Sensitivity and uncertainty analysis of βeff for MYRRHA using a Monte Carlo technique

G. V. D. Eynde, H. Iwamoto, L. Fiorito, 2018 .

Advanced Method for Calculations of Core Burn-Up, Activation of Structural Materials, and Spallation Products Accumulation in Accelerator-Driven Systems

G. V. D. Eynde, A. Stankovskiy, G. Eynde, 2012 .