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NSR database version of April 11, 2024.

Search: Author = G.Van den Eynde

Found 7 matches.

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2017FI01      Ann.Nucl.Energy 101, 359 (2017)

L.Fiorito, G.Zerovnik, A.Stankovskiy, G.Van den Eynde, P.E.Labeau

Nuclear data uncertainty propagation to integral responses using SANDY

NUCLEAR REACTIONS ²³Na(n, X), (n, n), E<20 MeV; calculated nuclear data uncertainties and covariances. ENDF/B, JEFF, JENDL evaluated nuclear data libraries.

doi: 10.1016/j.anucene.2016.11.026
Citations: PlumX Metrics

2016FI02      Ann.Nucl.Energy 88, 12 (2016)

L.Fiorito, A.Stankovskiy, G.Van den Eynde, C.J.Diez, O.Cabellos, P.E.Labeau

Generation of fission yield covariances to correct discrepancies in the nuclear data libraries

NUCLEAR REACTIONS ²³²Th, ^233,235,238U, ^239,241Pu(n, F), E=0.0000000253, 0.4, 14 MeV; calculated covariance matrices; deduced JEFF-3.1.1 library discrepancies. Comparison with available data.

doi: 10.1016/j.anucene.2015.10.027
Citations: PlumX Metrics

2014DI12      Nucl.Data Sheets 118, 516 (2014)

C.J.Diez, O.Cabellos, J.S.Martinez, A.Stankovskiy, G.Van den Eynde, P.Schillebeeckx, J.Heyse

Analysis of ²³⁸Pu and ⁵⁶Fe Evaluated Data for Use in MYRRHA

doi: 10.1016/j.nds.2014.04.122
Citations: PlumX Metrics

2014FI06      Ann.Nucl.Energy 69, 331 (2014)

L.Fiorito, C.J.Diez, O.Cabellos, A.Stankovskiy, G.Van den Eynde, P.E.Labeau

Fission yield covariance generation and uncertainty propagation through fission pulse decay heat calculation

NUCLEAR REACTIONS ²³⁵U(n, F)⁸⁸Br/⁸⁸Kr/⁸⁹Kr/⁹⁰Kr/⁹¹Kr/⁹²Kr/⁹²Rb/⁹³Rb/⁹⁵Rb/⁹⁴Sr/⁹⁵Sr/⁹⁶Sr/⁹⁷Sr/⁹⁷Y/⁹⁸Y/⁹⁹Y/⁹⁹Zr/¹⁰⁰Zr/¹⁰¹Zr/¹⁰²Zr/¹³²Sb/¹³³Sb/¹³²Te/¹³³Te/¹³⁴Te/¹³⁵Te/¹³⁶Te/¹³⁵I/¹³⁸I/¹³⁸Xe/¹³⁹Xe/¹⁴⁰Xe/¹⁴⁰Cs/¹⁴²Cs/¹⁴²Ba/¹⁴³Ba/¹⁴⁴Ba, E thermal; calculated fission product yield covariances and uncertainties. ACAB and ALEPH-2 libraries and codes.

doi: 10.1016/j.anucene.2014.01.038
Citations: PlumX Metrics

2014ST21      Nucl.Data Sheets 118, 513 (2014)

A.Stankovskiy, E.Malambu, G.Van den Eynde, C.J.Diez

Nuclear Data Needs for the Neutronic Design of MYRRHA Fast Spectrum Research Reactor

doi: 10.1016/j.nds.2014.04.121
Citations: PlumX Metrics

2013DI12      Ann.Nucl.Energy 60, 210 (2013)

C.J.Diez, A.Stankovskiy, E.Malambu, G.Zerovnik, P.Schillebeeckx, G.Van den Eynde, J.Heyse, O.Cabellos

Review of the ^natC(n, γ) cross section and criticality calculations of the graphite moderated reactor BR1

NUCLEAR REACTIONS C, ¹²C(n, γ), E<20 MeV; analyzed available data; deduced recommended σ, k_eff. Comparison with ENDF/B-VII.1, JENDL-4.0 evaluated libraries and EXFOR experimental library.

doi: 10.1016/j.anucene.2013.05.003
Citations: PlumX Metrics

2009RO18      Nucl.Technology 168, 537 (2009)

Y.Romanets, H.Ait Abderrahim, D.De Bruyn, R.Dagan, I.Goncalves, W.Maschek, G.Rimpault, D.Struwe, G.Van den Eynde, P.Vaz, C.Vicente

XT-ADS: Neutronics, Shielding, and Radiation Damage Calculations

doi: 10.13182/NT09-A9240
Citations: PlumX Metrics