| Credit Hours: | 2-3-3 |
| Prerequisites: | NRE 4204 or equivalent, or with the consent of the instructor |
| Catalog Description: | Concepts, computational techniques and theprincipal methods of criticality safety such as accident experience, standards, experiments, computer and hand calculations, limits, and regulations. Application to overall facility operation. |
| Textbooks: | Ronald A. Knief, Nuclear Criticality Safety: Theory and Practices, First Edition, American Nuclear Society, 1985 |
| Instructors: | Farzad Rahnema |
| References: | Computational Methods of Neutron Transport, Lewis and Miller, John Wiley and Sons, Inc., 1984 |
| Goals: | This course is to provide a comprehensive description of the nuclear criticality safety discipline. |
| Prerequisites by Topic: | Reactor Physics |
| Topics: | - Fundamentals
- Principles of Safety and Review of Reactor Theory
- Criticality Accidents
- Experiments
- Methods
- Accident Simulations
- Critical data
- Computational Methods
- S-N
- Monte Carlo
- Cross Sections
- Validations
- Subcritical Limits
- Double Contingency
- Hand Calculations
- Buckling/Shape Conversion
- Surface Density
- Solid Angle Method
- Standards, Regulations, Related Impacts and Practices
- Fuel Facility Applications
|
| Computer Usage: | Deterministic (e.g., TWODANT) and Monte Carlo (e.g. MCNP, KENO) Codes |
| Projects: | Critical experiment simulation and Criticality (storage) configuration simulation & design |
