A Nodal Method for Transient Analysis of Multigroup Neutron Diffusion
The purpose of the nodal model developed is to analyze the fast transient behavior of the reactor cores on the basis of time dependent multigroup neutron diffusion equation and precursor density equations given below. Although the current form of the model, which analyzes the transient behavior in one dimension without introducing the affects of the any feedback mechanisms such as temperature and Doppler affects, it is useful for gaining experience for further development of the model.
KeywordsDiffusion Equation Neutron Flux Legendre Polynomial Transient Behavior Adjacent Node
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