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)

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Part of:
Proceedings of 2009 international congress on advances in nuclear power plants

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)

Optional Information

Notes
Available as CD-ROM Data in PDF format, Folder Name: FinalPaper, Paper ID: 9292.pdf; 10 refs., 11 figs., 1 tab.