NUCLREN 4701
Transcript Abbreviation:
Intro Nucl Pwr Eng
Course Description:
For advanced undergraduates in nuclear engineering focusing on the physics and engineering of nuclear reactors and nuclear power plants.
Course Levels:
Undergraduate (1000-5000 level)
Designation:
Elective
General Education Course
(N/A)
Cross-Listings
(N/A)
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: 4505 (505) or MechEng 4505 (505); or permission of instructor.
Electronically Enforced:
No
Exclusions:
Not open to students with credit for 701.
Course Goals / Objectives:
Introduce the fundamental physical concepts relevant to the operation of nuclear reactors and nuclear power plants.
Introduce the fission reactor systems in current use.
Introduce the concepts involved with the design and operation of fission reactors (e.g. neutronics, fluid mechanics, and heat transfer).
Check if concurrence sought:
No
Contact Hours:
| Topic | LEC | REC | LAB | LAB Inst |
|---|---|---|---|---|
| Fission; Q-Values; Nuclear binding energy; Nuclear shell structure; Fissile vs. Fissionable isotopes Fertile isotopes and breeding; Neutron multiplication factor; | 3.0 | 0.0 | 0.0 | 0 |
| Macroscopic cross-section; Mean Free Path calculational details; Neutron-nuclear reactions; Formation of compound nucleus and cross-section resonances; Neutron flux, thermal utilization; eta; Infinite medium multiplication factor | 3.0 | 0.0 | 0.0 | 0 |
| Non-leakage probability; Neutron Diffusion Eqn; Derivation of Neutron Diffusion Equation; Derivation of Non-leakage Probability; Derivation of Extrapolation Distance; | 2.0 | 0.0 | 0.0 | 0 |
| Criticality Condition; Derivation of criticality condition and flux shape for 1-D slab reactor; | 2.0 | 0.0 | 0.0 | 0 |
| Right circular cylindrical core criticality condition and flux shape; Critical size for PWR; | 2.0 | 0.0 | 0.0 | 0 |
| Optimum height to diameter for cylindrical reactor; Heat flux | 2.0 | 0.0 | 0.0 | 0 |
| Definition of Hot Channel; Nuclear hot channel factor for cylindrical core; Power flattening | 2.0 | 0.0 | 0.0 | 0 |
| Criticality and Flux Shape for Reflected Slab Reactor; Reflector Savings | 1.0 | 0.0 | 0.0 | 0 |
| Thermal hydraulic analysis for PWR; Linear power density for PWR; PWR core area | 2.0 | 0.0 | 0.0 | 0 |
| Six Factor Formula and Two Group Diffusion Theory | 2.0 | 0.0 | 0.0 | 0 |
| Resonance Escape Probability and Neutron Thermalization; Figures of Merit for Moderators | 2.0 | 0.0 | 0.0 | 0 |
| Heterogeneous Effects in Reactor Cores | 2.0 | 0.0 | 0.0 | 0 |
| Doppler Reactivity Feedback; Moderator Reactivity Feedback | 2.0 | 0.0 | 0.0 | 0 |
| Commercial Nuclear Reactors, TMI | 2.0 | 0.0 | 0.0 | 0 |
| Point Reactor Kinetic Equations and Analysis of Step Reactivity Insertion | 2.0 | 0.0 | 0.0 | 0 |
| Overpower Factor and Design Margin | 1.0 | 0.0 | 0.0 | 0 |
| PWR Plant Operating Characteristics, PWR Simulation | 3.0 | 0.0 | 0.0 | 0 |
| Fission Product Poisoning | 2.0 | 0.0 | 0.0 | 0 |
| Total | 37 | 0 | 0 | 0 |
Grading Plan:
Letter Grade
Course Components:
Lecture
Grade Roster Component:
Lecture
Credit by Exam (EM):
No
Grades Breakdown:
| Aspect | Percent |
|---|---|
| Homework | 18% |
| Project | 2% |
| 2 Midterm Exams | 40% |
| Fianl Exam | 40% |
Representative Textbooks and Other Course Materials:
| Title | Author | Year |
|---|---|---|
| Introduction to Nuclear Engineering | Lamarsh and Baratta | |
| : Other unclassified public domain reference material will be provided to the students via the internet and OSU’s Carmen website |
ABET-CAC Criterion 3 Outcomes
(N/A)
ABET-ETAC Criterion 3 Outcomes
(N/A)
ABET-EAC Criterion 3 Outcomes
(N/A)
Embedded Literacies Info
(N/A)
Attachments
(N/A)
Additional Notes or Comments
(N/A)