Inhomogeneous point kinetics equations and the source contribution

Sathiyasheela, T.

doi:10.1016/j.nucengdes.2010.09.036

Cited by 4 publications

(3 citation statements)

References 6 publications

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“…Since the reactor is in sub-critical state in the cold start-up stage, the external neutron source cannot be ignored. Due to the low average temperature in the reactor core, here, the effect of temperature feedback can be ignored [9,19]; consequently, the NPK equations with the external neutron source term for one group of delayed neutrons can be written as follows [8,11,12,16]:…”

Section: Start-up Processmentioning

confidence: 99%

“…The neutron density is one of the most important parameters in reactor dynamics [5][6][7]. According to the importance of neutron density in the cold start-up stage, the external neutron source makes a significant contribution to the reactor power [8]. In most reactors, the reactivity is introduced mainly by discontinuous transferring of control rods which is, in practice, a linear function.…”

Section: Introductionmentioning

confidence: 99%

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Generalization of the analytical solution of neutron point kinetics equations with time-dependent external source

2014

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Point reactor kinetics equations with one group of delayed neutrons in the presence of the time-dependent external neutron source are solved analytically during the start-up of a nuclear reactor. Our model incorporates the random nature of the source and linear reactivity variation. We establish a general relationship between the expectation values of source intensity and the expectation values of neutron density of the sub-critical reactor by ignoring the term of the second derivative for neutron density in neutron point kinetics equations. The results of the analytical solution are in good agreement with the results obtained with numerical solution.

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Section: Start-up Processmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Generalization of the analytical solution of neutron point kinetics equations with time-dependent external source

2014

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“…During the initial reactor start-up, the reactor is in a subcritical condition and the external neutron source plays a crucial role from the reactor control point of view. Since in the reactor start-up process, the average temperature of the reactor core is lower and the power added is smaller, the temperature reactivity feedback mechanism can be neglected [1][2][3].…”

Section: Introductionmentioning

confidence: 99%

Solution of two-point reactor kinetic equations for source-driven reﬂected reactors using the Green's function generation method

Maleki

2020

Sinop Üniversitesi Fen Bilimleri Dergisi

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The transient analysis of nuclear reactors is a very important issue from the safety point of view. The point reactor kinetics equations are extensively used in the analysis of the transient behavior of the nuclear reactors. The experimental results confirm that the dynamical behavior of the strongly reflected reactors cannot be adequately characterized by the conventional onepoint reactor kinetics equations. In this study, a Green's function generation method is developed to solve the two-point reactor kinetics equations for a subcritical source-driven reflected reactor with one group of delayed neutron precursors during the reactor start-up. Moreover, the two-point reactor kinetics equations are solved using the prompt-jump approximation method and it is shown that the obtained results are in good agreement with the results obtained from the Green's function generation method. The validity of the given methodologies is also demonstrated through comparison with asymptotic solutions.

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Robust reactivity, neutron source, and precursor estimators for nuclear reactors

Ablay

2013

Nuclear Engineering and Design

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Inhomogeneous point kinetics equations and the source contribution

Cited by 4 publications

References 6 publications

Generalization of the analytical solution of neutron point kinetics equations with time-dependent external source

Generalization of the analytical solution of neutron point kinetics equations with time-dependent external source

Solution of two-point reactor kinetic equations for source-driven reﬂected reactors using the Green's function generation method

Robust reactivity, neutron source, and precursor estimators for nuclear reactors

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