University of Illinois at Urbana-Champaign, USA
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NPRE 457
Safety Analysis of Nuclear Reactor Systems
Professor
Assignments and Teaching Assistants
Assignments will account for 40 percent of the final grade.
NPRE 457 Fall 2022 First Midterm Exam
*****
NPRE 457 Fall 2022 Second Midterm Exam
*****
NPRE 457 Fall 2022 Third Exam
*****
Two midterm tests and one final test are scheduled.
Each will account for 20 percent of the final grade for a total of 60 percent of the final grade.
Assignments, quizzes (unannounced), final project, 40 percent.
Credit
Undergraduates: 3 hours of credit.
Graduates: 3 hours, 1 hour for advanced term paper or project, for a total of 4 hours of credit.
Calendar for Fall
Semester 2022
4039 Campus Instructional Facility, CIF
Class meeting: 3:00-3:50 pm, MWF
Instruction Begins | Monday, August 22 |
Labor Day | Monday, September 5 (no classes) |
General Election day | Tuesday November 8 (no classes) |
Thanksgiving Vacation Begins | Saturday, November 19 |
Instruction Resumes | Monday, November 28 |
Instruction Ends | Wednesday, December 7 |
Reading Day | Thursday, December 8 |
Final Examinations Begin | Friday, December 9 |
Final Examinations End | Friday, December 16 |
First Midterm |
Friday, September 30 |
Second Midterm |
Monday, October 31 |
Final Exam |
|
Textbook Manuscript
© M. Ragheb
Intellectual Property IP Protection
https://www.bbc.com/news/world-us-canada-64197625
https://www.bbc.com/news/entertainment-arts-59893035
PROBABILISTIC, POSSIBILISTIC AND DETERMINISTIC SAFETY ANALYSIS
Nuclear Applications
© M. Ragheb
Preface
1.
Overview
2.
Natural Disasters
and Man Made Accidents
3.
Safety
Definitions and Terminology
4.
Accidents Occurrence
5.
Risk Quantification
6.
Incidence and Likelihood Risk and Safety Indices
7.
The
Risk Assessment Methodology
8.
Risk and Safety Ethics
9.
The
Source Term
10.
Environmental Remediation of Radioactive Contamination
11.
Decay
Heat Generation in Fission Reactors
12. Cost
Effectiveness Analysis
13. Boolean Algebra
14.
Fuzzy de Morgan Algebra
15.
Probabilistic and Possibilistic Fault Tree Analysis
16. Event Tree Analysis
17. Random
Numbers Generation
18. Direct
Simulation or Analog Monte Carlo
19. Sampling
Methods
20. Sampling
Special Distributions
21.
Fluid
Mechanics Equations
22.
Safety Computational Fluid Dynamics
23. Loss of Coolant
Accident, LOCA
24.
Debris Bed Cooling
25. Steam Explosions
26.
Clad Ballooning Accident
27.
China Syndrome
28. Containment Structures
29. Safety
Aspects of Gas Cooled Reactors
30. Heavy Water Reactors
Safety
31.
Liquid Metal Reactors Postulated Accidents
32.
Autonomous
Battery Reactors
33. Fourth
Generation Reactor Concepts
34.
Inherently
Safe Reactor Designs
35. The Three Mile
Island Accident
36. Chernobyl Accident
37.
Experimental Breeder Reactor Number I, EBR I Criticality Accident
38.
Stationary Low Power Plant Number 1, SL-1 Accident
39.
Sodium-Graphite Reactor Experiment, SRE incident
40. Windscale Accident
41.
Fermi 1 Fuel Meltdown
Incident
42.
Steam Generator Leakage at the BN-350 Desalination Plant
43. Browns Ferry Fire
44. Earthquake Safety
44.
Fukushima Earthquake and Tsunami
Station Blackout Accident
45.
Global Climatic
Variation and Energy Use
46.
Solar Storms Effects on Nuclear and Electrical Installations
References
Appendices
I. Tacoma Narrows Bridge Collapse
II.
Procedure
to generate a decay curve, decay.f90
III. Procedure
to compute decay heat power and energy release, decayheat.f90
IV.
Fault
tree analysis code, sample14.f90
VI.
Input
file to sample14 program, insamp14.txt
VI. The
Panic Over Fukushima
Related Courses Information
NPRE402/ME405 Nuclear Power Engineering
NPRE457/CSE462 Safety Analysis of Nuclear Reactor Systems
NPRE490MC(NPRE456/CSE416) Monte Carlo Simulations
NPRE590SF Nuclear and Radiological Safety
NPRE459/CSE417 Fuzzy Logic and its Applications
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Last update for this page was on 4/6/2023.