Published 2009
| Version v1
Miscellaneous
Restricted
Numerical simulation of complex multi-dimensional two-phase flows in nuclear power plant coolant circuits by means of the best-estimate thermal-hydraulic code BAGIRA
- 1. All-Russian Research Institute for Nuclear Power Plant Operations, Moscow (Russian Federation)
Description
Recent results are exposed, obtained by applying the best-estimate thermal hydraulic code BAGIRA for three-dimensional modeling complex two-phase flow dynamics inside the vessel of the horizontal steam generator PGV-1000 used in reactor units with VVER-1000. Spatial volumetric void fraction and velocity distributions are calculated and compared with available experimental data. (author)
Files
Additional details
Publishing Information
- Imprint Title
- Proceedings of 2009 international congress on advances in nuclear power plants
- Imprint Pagination
- [2572 p.]
- Journal Page Range
- [9 p.]
- Report number
- INIS-JP--123
Conference
- Title
- 2009 international congress on advances in nuclear power plants
- Acronym
- ICAPP2009
- Dates
- 10-14 May 2009
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43084248
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- B CODES; COMPUTERIZED SIMULATION; DISTRIBUTION; MIXTURES; NUMERICAL ANALYSIS; STEAM GENERATORS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; TWO-PHASE FLOW; VELOCITY; VOID FRACTION; WWER TYPE REACTORS
- Descriptors DEC
- BOILERS; COMPUTER CODES; DISPERSIONS; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MATHEMATICS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: FinalPaper, Paper ID: 9292.pdf; 10 refs., 11 figs., 1 tab.