This course It does not provide sufficient experience to perform ab-initio accident analyses. It does not describe all categories of accidents and does not address every specific event included in the accident analyses.
This course is intended for engineers and licensed operators responsible for planning, analysis, and operational activities affected by accident analysis. No previous knowledge is required, but knowledge of major plant systems and understanding of reactor physics and core thermal-hydraulic concepts are helpful.
Applicable to: PWR.
Course Schedule:
- Course Introduction – The purpose and general methods of accident analysis Radiological Aspects of Nuclear Accidents – Identification and description of radioactive nuclides and their behavior during accident conditions Reactor Theory – Intrinsic reactivity effects, reactivity control, and reactor kinetics.
- Core Thermal Hydraulic Principles – Heat transfer mechanisms, departure from nucleate boiling, and natural circulation Introduction to Accident Analysis Methods.
- Increased Heat Removal by the Secondary System – Excessive turbine load, condensate and feedwater system malfunctions, and steam line break accidentsReduced Heat Removal by the Secondary System – Loss of normal load, loss of normal feedwater, and feed line break accidents.
- Reduced Reactor Coolant Flow – Partial loss of forced coolant flow, total loss of forced coolant flow, and natural circulationIncreased Reactor Coolant Inventory – Inadvertent safety injection actuation and malfunction of the chemical and volume control system.
- Reduced Reactor Coolant Inventory – Chemical and volume control pipe break outside of containment, theory of loss of reactor coolant accidents (LOCAs), and large-break LOCA.
- Intermediate and small-break LOCASteam Generator Tube Rupture.
- Introduction to Mitigating Core Damage – Concept and development of Emergency Response Guideline Critical Safety Functions Subcriticality Critical Safety Function – Evaluation of anticipated transient without scram (ATWS) events.
- Core Cooling Critical Safety Function – Evaluation of small-break LOCA without high-head Emergency Core Cooling System injectionHeat Sink Critical Safety Function – Evaluation of loss of all secondary heat sink event.
- Primary Integrity Critical Safety Function – Evaluation of pressurized thermal shock eventsContainment Critical Safety Function – Evaluation of containment over-pressure eventsSevere Accident Phenomenology – Adverse consequences of molten core debris. Accident Response of Instrumentation.
