Comparisons of RETRAN and two-velocity two-phase flow models with experimental data. Interim report
Description
Several aspects of two-phase flow models and computer programs associated with steady-state and transient analyses of nuclear steam supply systems have been investigated. The areas investigated include: comparisons of homogeneous equilibrium mixture and two-fluid model predictions with experimental data and with each other; numerical solution techniques; comparison of RETRAN predictions with experimental data; application of RETRAN to simple multi-dimensional flows; and derivation of macroscopic balance equations for two-fluid models of two-phase flows. The results of the investigations have shown the accuracy and ease of application of RETRAN, some of the limitations associated with homogeneous equilibrium mixture models of two-phase flow, and some of the areas in which RETRAN can be improved
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A15/MF A01.
Files
Additional details
Additional titles
- Augmented title (English)
- BWR; PWR
Publishing Information
- Imprint Pagination
- 341 p.
- Report number
- EPRI-NP--928
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10452732
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; R CODES; TWO-PHASE FLOW
- Descriptors DEC
- COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; FLUID FLOW; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS