Evaluation of two-fluid and drift flux thermohydraulics in APROS code environment
Description
The characteristics of the thermohydraulic solutions in APROS are considered for the nuclear power plant modelling. The thermohydraulic model of the APROS plant analyzer includes three levels of solutions, homogeneous 3-equation model, 5-equation drift flux model and 6-equation two-fluid model. In practical modelling of versatile process systems different approaches are selected for different types of the power plant sections. The 3-equation model is used for turbines and auxiliary systems. The 5-equation model and 6-equation model are alternative models for main process sections of the primary and secondary sides. The 5-equation model has been typically selected for the real time applications and the 6-equation model for the safety analysis applications. The validation needs for both approaches are the same. Because the change of the solution mode is an easy task in APROS, the validation tasks are typically performed in parallel for 5-equation and 6-equation models. By calculating in parallel with both models systematic errors in solutions may be pointed out. The testing against both separate effects tests and integral tests is an essential part in the thermohydraulics. In different plant applications different physical features are important. The analysis requirements vary from one application to another. When nodalizations together with increased computer speed are growing up, the earlier validation cases may be insufficient. That is why the content of the code has to be known in detail. Such an expertise in the code development has to be gained that properties of the code against other thermohydraulics codes are known. (author)
Files
Additional details
Publishing Information
- ISBN
- 951-38-5269-5
- Imprint Title
- Proceedings of the 2nd CSNI Specialist Meeting on Simulators and Plant Analysers
- Imprint Pagination
- 601 p.
- Journal Page Range
- p. 378-389
- Report number
- VTT-SYMP--194
Conference
- Title
- 2. CSNI Specialist Meeting on Simulators and Plant Analysers
- Dates
- 29 Sep - 2 Oct 1999
- Place
- Espoo (Finland)
INIS
- Country of Publication
- Finland
- Country of Input or Organization
- Finland
- INIS RN
- 31062764
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HEAT TRANSFER; HYDRAULICS; MANY-DIMENSIONAL CALCULATIONS; NUMERICAL SOLUTION; PRESSURE DEPENDENCE; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SIMULATORS; THERMAL ANALYSIS
- Descriptors DEC
- ANALOG SYSTEMS; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; FUNCTIONAL MODELS; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs.