Determination of neutron generation time in miniature neutron source reactor by measurement of neutronics transfer function

Dynamic analysis of the closed-loop transfer function in the miniature neutron source reactor (MNSR)

“…neutronics transfer function), where feedback effects are not employed and only the neutronics effect is dominant. In a former work (Hainoun and Khamis, 2000), this function was formulated on the basis of the point kinetic model using one-group precursor approximation in which six groups of delayed neutrons and nine groups of photo neutrons emitted from the beryllium reflector were lumped altogether (Smidt, 1971). The open-loop transfer function, that was verified experimentally using the technique of step change of reactivity, is given as (Hainoun and Khamis, 2000):…”

“…The neutronics data are available from the previous publication for the neutronics transfer function (Hainoun and Khamis, 2000). The temperature feedback coefficient of reactivity has been estimated experimentally to α T = −0.15224 mk/ • C (the reactivity unit mk is equal to 10 −3 , where k refers to the value 1 of the multiplication factor in critical condition [Smidt, 1971]) in range of 35-20 • C for the mean coolant temperature.…”

“…4 shows the measured relative neutron flux distribution after a step change of reactivity. Comprehensive description of the experimental methodology and data analysis is presented in (Hainoun and Khamis, 2000).…”

Dynamic Parameter Fitting of the Zed-2 Reactor Core Using a Neutron Flux Perturbation Experiment

“…Due to limitations on data acquisition (DAQ) and data analysis technique at that time, the results had fewer points in the curves and the quality was not high enough for dynamic parameter fitting. There was subsequently a long period of time when no similar study was found until some further publications reported the use of perturbation methods for obtaining dynamic parameters [10][11][12][13][14]. In these publications, the frequency of perturbation …”

Analyzing stability of neutron point kinetics equations with nine photo-neutron groups using Lyapunov exponent method

“…Neutron Point Kinetics photo-neutron into account are presented here for beryllium-moderated and heavy-water-moderated reactors [1,6,19,20] …”