NE 150 - Introduction to Nuclear Reactor Theory
Spring 2007
NE 150 - Introduction to Nuclear Reactor Theory
Spring 2007
Schedule : TuTh 2:00-3:30, 3102 Etcheverry Hall
Instructor : Professor T.J. Downar, 4105 Etcheverry Hall, 643-8085, email downar@ecn.purdue.edu
TA: Aurelie Niquille, aurelie_niquille@berkeley.edu
Office Hours: TBD
Part 1 (12 weeks). Reactor Statics: Neutron nuclear reactions, neutron chain fission reactors, neutron diffusion theory, neutron energy distributions.
Part 2 (3 weeks). Reactor Dynamics: Delayed fission neutrons, point kinetics equations, approximate solutions of the point kinetics equations, kinetics with reactivity feedback.
Prerequisites: NE101 (Nuclear Physics) or consent of instructor.
Grading:
A 100-90%, B 89-80%, C 79-70%, D 69-60%, F <60%.
30% Homework, 70% 2 Exams
K. O. Oft and W. A. Bezella, "Introductory Nuclear Reactor Statics," Revised Edition, American Nuclear Society (1989)
K. O. Oft and R. J. Neuhold, "Introductory Nuclear Reactor Dynamics," American Nuclear Society (1985)
References :
A. Henry, "Nuclear Reactor Analysis," MIT Press (1975)
W. Stacey, "Nuclear Reactor Physics," Wiley & Sons (2001)
J. Duderstadt, "Nuclear Reactor Analysis," Wiley & Sons (1976)
Topics Part 1. Reactor Statics
1. Review of basic concepts: neutron reaction cross sections, fission, fluxes, currents and sources (1/2 week).
2. Neutron balance equations: diffusion equations (1, 2 and 3 dimensional, energy dependent and multi group), differential and integral transport equations, boundary and interface conditions, balance equations in operator form (2 weeks).
3. Fundamental neutronics problems: source sink and subcritical problems, criticality (1 week).
4. Separation of space and energy dependencies, solution of the separated balance equations, the material buckling (1 week).
5. Space dependence of the flux in various geometries, one group source problems, separated source problems, the exponential pile (1 week).
6. Multiregion problems, the reflector savings (1/2 week).
7. Two group flux solutions, degree of flux separability (1 week).
8. Scattering processes: potential scattering, resonance scattering, inelastic scattering, energy and angular distributions, scattering kernels (1 week).
9. Slowing down theory, numerical solution, analytical solution, thermalization of neutrons, thermal neutron spectra (2 weeks).
10. Slowing down theory with resonance absorption: resonance physics, resonance absorption, resonance integrals, resonance escape probability (1.5 weeks).
Total Reactor Statics: 11 weeks.
Topics Part 2. Reactor Kinetics and Dynamics
1. Delayed neutrons, preliminary formulation of the point kinetics equations (1 week).
2. Kinetics with constant reactivity, the inhour equation, general solutions, approximate point kinetics: prompt jump approximation (PJA), prompt kinetics approximation, flux trajectories in PJA for sub and supercritical transients for time dependent reactivity (1 week).
3. Reactor dynamics, transients with feedback: feedback effects, the feedback reactivity, super prompt bursts, accident energy release, dependence of the accident energy release on neutron generation time (graphite moderated reactor vs. LWR), dependence of the accident energy release on the neutron flux level (loading accidents vs. full power accidents) (1 week).
Total Reactor Kinetics and Dynamics: 3 weeks.
Course Computer Accounts and Computer Laboratories: