Numerical calculation of neutron fluxes at the exit of a complex neutron-guide system at IRI, Delft von Pusenkov, V.M., Schebetov, A., Gibcus, H.P.M., Gommers, R.M., Labohm, F., de Haan, V.O., van Well, A.A.

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A new method to determine in situ the transmission of a neutron-guide system at a reactor source von de Haan, V.O, Gibcus, H.P.M, Gommers, R.M, Labohm, F, van Well, A.A, de Leege, P.F.A, Schebetov, A, Pusenkov, V

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Research reactor in-core fuel management optimization by application of multiple cyclic interchange algorithms von van Geemert, R, Quist, A.J, Hoogenboom, J.E, Gibcus, H.P.M

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Thermal hydraulic model validation for HOR mixed core fuel management von Gibcus, H.P.M, de Vries, J.W, de Leege, P.F.A

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