Fission and power from fission: Review, Characteristics of fission, neutron physics, practical fission fuels.

Neutron-Chain reacting systems: Multiplication factor, self sustained chain reactions, four factor formula for infinite and finite thermal assemblies, conversion and breeding reactions, types of nuclear reactors, general considertation of reactor design, reactor safety.

The diffusion of neutrons: neutron current density, the equation of continuity, Fick’s law, transport corrections, the diffusion equation, boundary conditions for steady-state diffusion equation, elementary solutions of the steady state diffusion equation, comparison of solutions for finite and infinite medium, diffusion length.

Neutron moderation: energy loss in elastic scattering, average logarithmic energy decrement, slowing down power, moderating ration, lenthargy, collision and slowing down densities, moderation of neutrons in hydrogen (without absorption), mediation of neutrons in hydrogen with absorption, spatial distribution of neutrons, Fermi age equation, solution of Fermi age equation in an infinite region, physical significance of Fermi age.

Fermi theory of bare thermal reactor: criticality of an infinite homogenous reactor, the approach to critical and the critical condition, material and geometric buckling, critical size and composition calculations for reactors of various types.

Multi region reactors: introduction, the group diffusion method; group constants, one group of neurons, steady-state diffusion equation for a core-reflector system, solution, solution of the diffusion equation for an infinite slab reactor with reflector and for a symmetrical, reflected reactor with spherical core, reflector, general properties, reflector savings, relation between reflector savings and maximum to average neutron flux in slab reactor, two groups of neutrons—qualitative discussion, neutron flux distribution in core and reflector.

Heterogeneous reactors: (natural uranium); introduction, thermal neutron fission, requirements and limitations, possible alternative, properties of heterogeneous system, resonance capture and resonance escape probability, calculation of the thermal utilization, resonance escape probability and fast fission factor.

Commercial reactors: Pressurized Water Reactor (PWR), Boiling Water Reactor (BWR), Heavy Water Reactor (HWR), Gas Cooled Reactor (GCR), Water Moderated Enriched Reactors, future of nuclear fission power, The breeder reactor, Accelerator- Driven System.

Recommended Text:
1. R. L. Murray, “ Nuclear Physics”, 5th ed. Butterworth, Heineman (2001).
2. D. J. Bannet and J. R Thomson,” The elements of nuclear power” Longman Scientific and Technical (1989).
3. S. Glasstone and A. Sesonkee, ”Nuclear Reactor Engineering” 3rd ed. D. Van Nostrand Co. (1986).
4. J. R Lamarsh, “ Introduction to nuclear reactor theory” Addison Wisley (1966).
5. S. Glasstone and M.C Edlund, “ The elements of nuclear reactor theory” D. Van Nostrand Co. (1952).