Lecture

Neutron Diffusion Equation: Numerical Methods

In course

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Description

This lecture covers numerical methods for solving the neutron diffusion equation, including finite difference formulation and dealing with the neutron source. It discusses the explicit k-eigenvalue problem, power iteration scheme, and the numerical solution to a 1D/2G slab reactor. The lecture also addresses the determination of group constants, energy self-shielding, and heterogeneous effects in thermal reactors.

Instructors (2)

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Official source

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Ontological neighbourhood

Energy engineering

Nuclear power: Topics in nuclear power

Mathematics

Analysis: Numerical analysis

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