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Lecture
Neutron Diffusion Equation: Numerical Methods
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Multigroup Theory: Main Equations and Numerical Solution
Covers the derivation of multi-group diffusion equations and the numerical methods for solving the neutron diffusion equation.
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Explores reactivity variations in reactor technology, covering short-term, medium-term, and long-term effects, means of control, and consequences.
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Covers media containing fuel, analytical solutions, and non-leakage probability for thermal and fast neutrons.
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Explores chain reactions, criticality, reactor types, and fuel cycles in nuclear engineering.
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Explores the modified one group theory for thermal reactors, focusing on media containing fuel and resonance treatment.
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Explores the fundamentals and challenges of nuclear reactors, covering neutron diffusion, fission, breeding, transmutation, and advanced technologies.
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Explores reactivity variations, control mechanisms, and the impact of the Doppler effect on reactor temperature.
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