Lectures: 2 sessions / week, 1.5 hours / session
This course is intended to understand the engineering design of nuclear power plants using the basic principles of reactor physics, thermodynamics, fluid flow and heat transfer.
This course includes the following: Reactor designs, Thermal analysis of nuclear fuel, Reactor coolant flow and heat transfer, Power conversion cycles, Nuclear safety and Reactor dynamic behavior.
Henry, A. F. Nuclear-Reactor Analysis. Cambridge, MA: MIT Press, 1975. ISBN: 9780262080811.
Plagiarism—use of another's intellectual work without acknowledgement—is a serious offense. It is the policy of the Literature Faculty that students who plagiarize will receive an F in the subject, and that the instructor will forward the case to the Committee on Discipline. Full acknowledgement for all information obtained from sources outside the classroom must be clearly stated in all written work submitted. All ideas, arguments, and direct phrasings taken from someone else's work must be identified and properly footnoted. Quotations from other sources must be clearly marked as distinct from the student's own work. For further guidance on the proper forms of attribution, consult the style guides available at the Writing and Communication Center and the MIT Web site on Plagiarism.
|LEC #||TOPICS||KEY DATES|
Nuclear power overview
|2||Nuclear power overview (cont.)|
|3||Reactor physics review|
|4||Reactor physics review (cont.)||Pset 1 due|
|5||Thermal parameters + conservation equations|
|6||PWR and BWR description||Pset 2 due|
|7||Other reactor designs (heavy water, gas, liquid metal)|
|8||Thermal analysis of fuel elements (introduction to fuels and heat conduction equation)||Pset 3 due|
|9||Thermal analysis of fuel elements (temperature distributions + core max temperature)|
|10||Ideal gas and incompressible fluid models + single-phase coolant flow (pressure drop and natural circulation)||Pset 4 due|
|11||Single-phase coolant heat transfer (correlations + heat exchangers)|
|13||Pure substance model two-phase coolant flow (parameters)||Pset 5 due|
|14||Two-phase coolant flow and heat transfer (pressure drop + boiling)||Pset 6 due|
|15||Two-phase coolant heat transfer (boiling crises + demos)|
|16||Power cycles (Rankine)||Pset 7 due|
|17||Power cycles (Brayton)|
|18||Nuclear safety (pillars + thermal limits + protection system + ECCS + severe accidents + containment)||Pset 8 due|
|19||Structural mechanics (elasticity fundamentals + thin-shell theory)||Pset 9 due|
|20||Structural mechanics (stress limits)|
|21||Visit to the Seabrook Nuclear Power Station|
|22||Dynamic behavior of PWR (with use of PRISM simulator)||Pset 10 due|
|23||Dynamic behavior of BWR (with use of IAEA simulator)|
|25||Final exam review|