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BASIS OF MODELING OF THERMAL HYDRAULIC PROCESSES IN NUCLEAR REACTORS
Contents
1. Introduction
2. Mass, momentum and energy conservation laws
3. Basis for the development of models for two phases flows
4. Codes for the analysis of accident and transient processes at NPPs
4.1. Thermal-hydraulic system codes
4.2. Reactor dynamics codes including coupled codes
4.3. Containment thermal-hydraulics codes
5. Main assumptions and principles of deterministic analysis
5.1. Analytical assumptions
5.2. Principles of deterministic analysis
6. Grouping of initiating events
7. Acceptance criteria for safety evaluation
8. Best estimate approach for licensing process
9. Modeling of processes in reactor cooling system
9.1. Development of Reactor Cooling System model for RBMK-1500
9.2. Development of Reactor Cooling System model for PWR reactor
10. Employment of coupled neutronic/thermal-hydraulic codes
10.1. Thermal-hydraulic model
10.2. Nodal kinetics model
10.3. Reactor control system model
11. Validation and verification of models
11.1. Validation of models by employing separate effects tests data
11.2. Validation of models by employing operational data
12. Example of the analysis of postulated accidents
13. Nomenclature and abbreviations
14. References

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