NUCLREN 4536
Transcript Abbreviation:
Nuclear ReactorSys
Course Description:
Introductory course covering concepts of nuclear power reactor systems, thermal and mechanical design aspects and economics of nuclear power plants.
Course Levels:
Undergraduate (1000-5000 level)
Designation:
Required
Elective
General Education Course:
(N/A)
Cross-Listings:
Cross-listed in MechEng.
Credit Hours (Minimum if “Range”selected):
3.00
Max Credit Hours:
(N/A)
Select if Repeatable:
Off
Maximum Repeatable Credits:
(N/A)
Total Completions Allowed:
(N/A)
Allow Multiple Enrollments in Term:
No
Course Length:
14 weeks (autumn or spring)
12 weeks (summer only)
Off Campus:
Never
Campus Location:
Columbus
Instruction Modes:
In Person (75-100% campus; 0-24% online)
Prerequisites and Co-requisites:
Prereq: 4505 (505) or MechEng 4505 (505); or permission of instructor.
Electronically Enforced:
No
Exclusions:
Not open to students with credit for 6536 (736), MechEng 4536 or 6536 (736).
Course Goals / Objectives:
To become aware of the basic designs of nuclear power reactor systems
To understand the fundamental principles of reactor design with an emphasis on reactor thermal design
To understand the thermodynamics of operating nuclear power plants (BWRs and PWRs)
To understand the shut-down power generation
Be able to analyze a simple Brayton power cycle
Be able to perform a simplified transient analysis for a nuclear power plant following a postulated LOCA
Be able to calculate the steady-state temperature profile in a fuel pin
Check if concurrence sought:
No
Contact Hours:
| Topic | LEC | REC out-of-class | REC in-class | Weekly LAB out-of-class | Weekly LAB in-class |
|---|---|---|---|---|---|
| Reactor types and their major design features (PWRs, BWRs, LMFBRs, Gas-cooled Reactors) | 5.0 | 0.0 | 0 | 0.0 | 0 |
| Reactor design principles (Reactor core design, Fuel design, Thermal design, Material considerations, Control and safety, and Economics) | 2.0 | 0.0 | 0 | 0.0 | 0 |
| Thermal design principles (Power peaking factors, Pool boiling curve, Critical heat flux) | 2.0 | 0.0 | 0 | 0.0 | 0 |
| Reactor heat generation (Heat generation profile in idealized reactors, Power peaking factors, Heat generation in fuel, moderator, and structure, Reactor shutdown heat generation) | 3.0 | 0.0 | 0 | 0.0 | 0 |
| Single-phase flow analysis (General balance equation, Control volume analysis) | 3.0 | 0.0 | 0 | 0.0 | 0 |
| Introduction to two-phase flow | 2.0 | 0.0 | 0 | 0.0 | 0 |
| Review of first and second laws of thermodynamics | 1.0 | 0.0 | 0 | 0.0 | 0 |
| Thermodynamic analysis of nuclear power plants (Rankine cycle, Co-generation with feedwater heaters, moisture separator, Brayton cycle) | 4.0 | 0.0 | 0 | 0.0 | 0 |
| Transient first law analysis (BWR Blowdown, Containment pressure response during a LOCA, PWR pressurizer response to load change) | 3.0 | 0.0 | 0 | 0.0 | 0 |
| Thermal analysis of fuel elements | 2.0 | 0.0 | 0 | 0.0 | 0 |
| Lessons learnt from the TMI accident | 1.0 | 0.0 | 0 | 0.0 | 0 |
| Total | 28 | 0 | 0 | 0 | 0 |
Grading Plan:
Letter Grade
Course Components:
Lecture
Grade Roster Component:
Lecture
Credit by Exam (EM):
No
Grades Breakdown:
| Aspect | Percent |
|---|---|
| Homework | 30% |
| Midterm | 30% |
| Final Exam | 40% |
Representative Textbooks and Other Course Materials:
| Title | Author | Year |
|---|---|---|
| Nuclear System I, Thermal Hydraulic Fundamentals | 1. Todreas, N.E. and Kazimi, M.S. |
ABET-CAC Criterion 3 Outcomes:
(N/A)
ABET-ETAC Criterion 3 Outcomes:
(N/A)
ABET-EAC Criterion 3 Outcomes:
| Significant contribution (7+ hours) | 1 | an ability to identify, formulate, and solve complex engineering problems by applying principles of engineering, science, and mathematics |
| Some contribution (1-2 hours) | 4 | an ability to recognize ethical and professional responsibilities in engineering situations and make informed judgments, which must consider the impact of engineering solutions in global, economic, environmental, and societal contexts |
Embedded Literacies Info: