Courses:

Neutron Science and Reactor Physics >> Content Detail



Syllabus



Syllabus

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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



ACTIVITIESPERCENTAGES
Homework20%
Four exams (20% each; lowest grade is dropped)60%
Final exam (3.0 hours)20%



Calendar



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

 








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