Course Meeting Times
Lectures: 2 sessions / week, 1.5 hours / session
Course Description
This course provides an in-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, thorium and other fuel types, reprocessing and waste disposal. Also covered are the principles of fuel cycle economics and the applied reactor physics of both contemporary and proposed thermal and fast reactors. Nonproliferation aspects, disposal of excess weapons plutonium, and transmutation of actinides and selected fission products in spent fuel are examined. Several state-of-the-art computer programs are provided for student use in problem sets and term papers.
Grading
| ACTIVITIES | PERCENTAGES |
|---|---|
| Homework | 30% |
| Computer laboratory | 20% |
| Mid-term presentation | 10% |
| Term paper | 30% |
| Final presentation | 10% |
MIT Statement on Plagiarism
Plagiarism—use of another’s intellectual work without acknowledgement—is a serious offense. It is the policy of the 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.
Calendar
| LEC # | TOPICS | KEY Dates |
|---|---|---|
| 1 | Introduction – Front End Overview | |
| 2 | Front & Design Center | |
| 3 | Core Design Criteria - Physics |
Problem Set 1 due |
| 4 | Core Design Criteria - Engineering | |
| 5 | In-Core Aspects |
Problem Set 2 and Lab 1 due |
| 6 | In-Core Aspects (cont.) | |
| 7 | Fuel Cycle & Operations Economics | Problem Set 3 due |
| 8 | Fuel Cycle & Operational Economics (cont.) | |
| 9 | Fast Reactors |
Problem Set 4 and Lab 2 due |
| 10 | HTGR | Problem Set 5 due |
| 11 | CANDU Physics, Fuel Cycle, Limits | |
| 12 | High Level Waste | Lab 3 due |
| 13 | Coupled Reactor Analysis | Problem Set 6 due |
| 14 | Lab Period / Tutorial | |
| 15 | Initial Project Presentations | |
| 16 | Initial Project Presentations (cont.) | Problem Set 7 due |
| 17 | Options for Actinide Management 1 | Lab 4 due |
| 18 | Covering Lab #4 / Discussing Lab #5 | |
| 19 | Fuel Manufacturing & Eng. Design | Problem Set 8 due |
| 20 | Proliferation Extrinsic Issues 1 | |
| 21 | Fuel Performance During Irradiation | Problem Set 9 due |
| 22 | Thorium Fuel Cycles | Lab 5 due |
| 23 | Lab #5 Discussion | |
| 24 | Options for Actinide Management 2 | |
| 25 | Actinide Separation Technology | |
| 26 | Fuel Cycle Systems Simulation | Term Paper due |
| 27 | Term Paper Presentations | |
| 28 | Term Paper Presentations (cont.) |
