Validation of RETRAN-03 against a wide range of rod bundle void fraction data
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:426538
- Paul Scherrer Inst., Villigen (Switzerland)
The work reported in this paper is a validation of the RETRAN-03 code`s ability to calculate the void fraction in a reactor core and so presents an assessment of the code against a wide range of void fraction measurements in rod bundles. The current version of RETRAN (RETRAN-03) uses the Chexal-Lellouche void fraction correlation as the basis for the calculation of the liquid vapor slip, either in the framework of a drift-flux model or as the basis of its dynamic slip model. The current assessment is based on data sets not included in the original correlation database. The data sets are from experimental facilities in Switzerland (NEPTUN-111), France (PERICLES), the United Kingdom (THETIS), and Japan: the Large-Scale Test Facility (LSTF) and the Two-Phase Flow Test Facility (TPTF).
- OSTI ID:
- 426538
- Report Number(s):
- CONF-961103--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 75; ISSN TANSAO; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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