
B.S. REACTOR PHYSICS [PHYS678] SYLLABUS

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

NeutronChain 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 steadystate 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, steadystate diffusion
equation for a corereflector 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).



