NRE 6434 - NUCLEAR CRITICALITY SAFETY ENGINEERING
Offered as Required
| Credit Hours | 2-3-3 | |
| Prerequisite: | NRE 4204 or equivalent, or with the consent of the instructor | |
| Course 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. | |
| Textbook: | Ronald A. Knief, Nuclear Criticality Safety: Theory and Practices, First Edition, American Nuclear Society, 1985 | |
| Instructor: | 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
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| Classes: | Topics |
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| 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 | |
| Design Projects: |
Critical experiment simulation and Criticality (storage) configuration simulation & design | |
Prepared by: F. Rahnema
Date: 9/1/96
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Revised July 2004