Course Number: NPRE 555
Title: Reactor Theory I
Catalogue Description: Advanced development of neutron transport theory; neutron slowing-down and resonance absorption; approximations to the transport equation; direct numerical methods and other techniques of approximation theory applied to the neutron transport equation; advanced topics.
| Principle Topics Covered | Hours (Approximate) |
|---|---|
| Fundamentals of Neutron Transport Theory | 9 |
Neutron Balances in Phase Space |
|
The Integro-differential Neutron Transport Equation |
|
The Adjoint Equation |
|
Probability Balances and Neutron Importance |
|
The Integral Transport Equation |
|
One-speed Transport Theory (Thermalization, "one-speed" thermal and fast neuts.) |
|
Exact solutions in One-speed Transport Equation |
|
Green's Functions for the Transport Equation |
|
Reciprocity Theorems for the Transport Equation |
|
The Multigroup Transport Equations |
|
| Fundamentals of Neutron Slowing-down Theory | 7 |
Exact Solutions for Slowing-down in an Infinite Medium (Hydrogen, A>1 without absorption, hydrogen with a heavy absorber) |
|
Approximate Solutions for Slowing-down in an Infinite Medium with Absorptic (Narrow resonance approximation, narrow resonance, infinite mass approximate slowly varying absorption, the Wigner and Greuling-Goertzel approximations) |
|
| Approximations to the One-speed, Multigroup and Continous Energy-dependent Transport Equations | 6 |
Polynomial Expansions of the Angular Flux (PN and DPN approximations) |
|
Diffusion Theory, Fundamental Mode Diffusion Theory |
|
Asymptotic Transport Theory (BN approximation) |
|
| Direct Numerical Solutions | 6 |
Algorithms for the One-speed and Multigroup Diffusion Equations |
|
Algorithms for the Integro-differentia and the Integral Forms of the One-speed and Multigroup Transport Equations |
|
| Applications of Elementary Approximation Theory Techniques to the Neutron Transport Equation | 8 |
Variational Methods, Linear Vector Space Methods, Weighted Residual Methods, Perturbation Theory |
|
Special Cases (Multigroup equations, flux weighting, adjoint weighting, bilinear weighting, PN equations. |
|
| Combinations of Techniques in Practical Reactor Analysis | 2 |
Multigroup Cross Section Sets |
|
Calculations (Infinite medium, fundamental mode diffusion theory, asymptotic reactor theory, diffusion theory, transport |
|
Group Collapsing of Cross Sections |
|
Criticality Calculations |
|
The Quasi-Static Method and Related Approximations |
|
Synthesis Methods (Time Synthesis, Space-Time Synthesis) |
|
Special methods for the Stiff Partial Differential Equations of Space-Time Kinetics |
|
| Advanced Topics (to be drawn from the subjects listed above and from current research) | 5 |
| Examinations | 2 |
| Total | 45 |
Basic Texts: Basic sources include the research papers published in journals together with ERDA R & D reports and overseas R & D reports from England, Germany, France & Italy.
Reference books:
Prerequisites: NPRE 560, Reactor Kinetics and Dynamics; or Graduate standing in Physics; or consent of instructor.
Purpose of Course:
Instructor: Roy Axford
Credit:
Meeting hours per week: 3
Class registration opacity: 20
Semesters course offered: REFER TO MASTER LISTING
Other notes:
Course last revised: