This is an archived course. A more recent version may be available at ocw.mit.edu.

Syllabus

Course Meeting Times

Lectures: 3 sessions / week, 1 hour / session

Recitations: 1 session / week, 2 hours / session

Course Objective

The central problem of reactor physics can be stated quite simply. It is to compute, for any time t, the characteristics of the free-neutron population throughout an extended region of space containing an arbitrary, but known, mixture of materials. Specifically we wish to know the number of neutrons in any infinitesimal volume dV that have kinetic energies between E and E + ΔE and are traveling in directions within an infinitesimal angle of a fixed direction specified by the unit vector Ω.

If this number is known, we can use the basic data obtained experimentally and theoretically from low-energy neutron physics to predict the rates at which all possible nuclear reactions, including fission, will take place throughout the region. Thus we can predict how much nuclear power will be generated at any given time at any location in the region.

Textbooks

The text book for this course is:

Amazon logo Lamarsh, John. Introduction to Nuclear Engineering. 3rd ed. Englewood Cliffs, NJ: Prentice Hall, 2001. ISBN: 9780201824988.
This covers basic reactor physics as part of a complete survey of nuclear engineering.

Readings may also be assigned from certain of the books listed below:

Amazon logo Henry, A. F. Nuclear Reactor Analysis. Cambridge, MA: MIT Press, 1975. ISBN: 9780262080811.

Amazon logo Shultis, J., and R. Faw. Fundamentals of Nuclear Science and Engineering. New York, NY: Marcel Dekker, 2002. ISBN: 9780824708344.

Amazon logo Hewitt, G., and J. Collier. Introduction to Nuclear Power. New York, NY: Taylor and Francis, 2000. ISBN: 9781560324546.

Amazon logo Turner, J. Atoms, Radiation, and Radiation Protection. New York, NY: Pergamon Press, 1986. ISBN: 9780080319377.

Amazon logo Kneif, R. Nuclear Criticality Safety: Theory and Practice. American Nuclear Society, 1985. ISBN: 9780894480287.

Amazon logo Knoll, G. Radiation Detection and Measurement. New York, NY: Wiley, 2000. ISBN: 9780471073383.

Grading Policy

ACTIVITIES PERCENTAGES
Homework 20%
Four exams (20% each; lowest grade is dropped) 60%
Final exam (3.0 hours) 20%

 

Calendar

Lec # Topics
1 Introduction/reactor layout and classification
2 Chart of nuclides/neutron sources
3 Neutron reactions/Boltzman distribution/number density
4 Neutron cross-sections
5 Binding energy/liquid drop model/fission process
  Tour of MIT research reactor
6 Burners, converters, breeders/neutron life cycle
7 Neutron life cycle
8 Criticality accidents/why is radiation dangerous
9 Neutron flux, reaction rates, current
10 One velocity model
  Exam 1
11 Non-multiplying media
12 Multiplying media
13 Criticality conditions
14 Kinematics of neutron scattering
15 Group diffusion method
16 Solution of group equations
  Exam 2
17 Energy dependence of flux
18 Group theory/four factor formula
19 Reactors of finite size
20 Reactors of multiple regions: One group
21 Reactors of multiple regions: Two group
22 Application of the two-group equations
23 Few group and multi-group approaches
24 Monte Carlo analysis
  Exam 3
25 Subcritical multiplication and reactor startup
26 Reactor operation without feedback
27 Analytic solution of reactor kinetics
28 Dynamic period and inhour equation
29 Reactor operation with feedback effects
30 Achievement of feedback effects/Chernobyl
  Exam 4
31 Shutdown margin/review of TMI
  Review