“…The prompt jump approximation is not new to nuclear reactor kinetics; it has been applied to point kinetics (space-independent kinetics) problems for many years 13,14 Therefore, the'prompt jump approximation is introduced by way of point kinetics in Section 2. The prompt jump approximation may be applied to any of the mathematical models of nuclear reactor kinetics which were described in Chapter 1: the Boltzman transport model, the diffusion theory model and the point kinetics model.…”
“…The prompt jump approximation is not new to nuclear reactor kinetics; it has been applied to point kinetics (space-independent kinetics) problems for many years 13,14 Therefore, the'prompt jump approximation is introduced by way of point kinetics in Section 2. The prompt jump approximation may be applied to any of the mathematical models of nuclear reactor kinetics which were described in Chapter 1: the Boltzman transport model, the diffusion theory model and the point kinetics model.…”
“…The multi-energy group nuclear reactor kinetics equations with multi-group delayed neutrons can be written in the following form [5]: Using the finite difference method, the equations (1) and (2) lead to the following matrix form…”
Section: The Time Dependent Neutron Diffusion Problemmentioning
“…The performance of these smoothing filters are tested for a step-change in reactivity in a nuclear reactor model governed the point-kinetic equations [10] given by (12)- (13) with { } , , P C ρ being the reactor power, delayed neutron precursor concentration and reactivity respectively. The measured power signals by the SPND are considered to be transmitted through the LAN from the reactor house to the control room or RRS.…”
Section: E Application In Networked Nuclear Reactor Controlmentioning
confidence: 99%
“…prompt neutron and delayed neutron [10]. At the start up conditions of nuclear reactor or at setpoint changes, the random delays are highly detrimental especially for the prompt neutron jump and may cause rapid growth of global power and cause thermal shock to its elements.…”
Abstract-This paper analyzes a nuclear reactor power signal that suffers from network induced random delays in the shared data network while being fed-back to the Reactor Regulating System (RRS). A detailed study is carried out to investigate the self similarity of random delay dynamics due to the network traffic in shared medium. The fractionality or selfsimilarity in the network induced delay that corrupts the measured power signal coming from Self Powered Neutron Detectors (SPND) is estimated and analyzed. As any fractional order randomness is intrinsically different from conventional Gaussian kind of randomness, these delay dynamics need to be handled efficiently, before reaching the controller within the RRS. An attempt has been made to minimize the effect of the randomness in the reactor power transient data with few classes of smoothing filters. The performance measure of the smoothers with fractional order noise consideration is also investigated into.
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