NUCLREN 6537
Transcript Abbreviation:
Nuc Reac Ther Hydr
Course Description:
Focuses on heat transfer and fluid flow applications in nuclear power reactor systems, including heat transfer in LWR fuel rods, coolant, and reactor internals.
Course Levels:
Graduate
Designation:
Elective
General Education Course:
(N/A)
Cross-Listings:
Cross-listed in MechEng.
Credit Hours (Minimum if “Range”selected):
3.00
Max Credit Hours:
3.00
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: 6536 (736) or MechEng 6536 (736), or equiv, or permission of instructor.
Electronically Enforced:
No
Exclusions:
Not open to students with credit for 737 or MechEng 6537 (737).
Course Goals / Objectives:
Provide a systematic treatment of reactor thermal hydraulics for LWRs, with a focus on one-dimensional analysis
Understand the fundamentals of single-phase fluid flow and heat transfer
Understand the fundamentals of two-phase fluid flow and heat transfer, including two-phase pressure drop, boiling heat transfer, and condensation
Be aware of various two-phase flow models and understand their application domains and limitations
Perform steady-state and transient analysis for a nuclear reactor fuel assembly
Check if concurrence sought:
No
Contact Hours:
Topic | LEC | REC | LAB | LAB Inst |
---|---|---|---|---|
General balance equation | 2.0 | 0.0 | 0.0 | 0 |
Single-phase flow conservation equations and constitutive equations | 2.0 | 0.0 | 0.0 | 0 |
One-dimensional single-phase flow formulation and closure relations | 3.0 | 0.0 | 0.0 | 0 |
Basic concepts and parameters in two-phase flow | 2.0 | 0.0 | 0.0 | 0 |
Separate flow: Surface wave (Rayleigh-Taylor instability and Kelvin-Helmholtz instability) | 2.0 | 0.0 | 0.0 | 0 |
Two-phase flow models | 3.0 | 0.0 | 0.0 | 0 |
Closure relations and correlations for two-phase flow | 3.0 | 0.0 | 0.0 | 0 |
One-dimensional two-phase flow formulations and closure relations | 2.0 | 0.0 | 0.0 | 0 |
Two-phase pressure drop | 2.0 | 0.0 | 0.0 | 0 |
Boiling heat transfer | 2.0 | 0.0 | 0.0 | 0 |
Condensation heat transfer | 2.0 | 0.0 | 0.0 | 0 |
Single heated channel transient analysis | 3.0 | 0.0 | 0.0 | 0 |
Total | 28 | 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 exam | 30% |
Final exam | 40% |
Representative Textbooks and Other Course Materials:
Title | Author | Year |
---|---|---|
Nuclear System I, Thermal Hydraulic Fundamentals | 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:
(N/A)
Embedded Literacies Info:
Attachments:
(N/A)
Additional Notes or Comments:
(N/A)
Basic Course Overview:
NUCLREN_6537_basic.pdf
(10.79 KB)