Thermal Hydraulic Characteristics of a Double-Walled Tube Advanced Nuclear Steam Generator
- 1 January 1989
- journal article
- research article
- Published by Taylor & Francis in Heat Transfer Engineering
- Vol. 10 (3) , 25-35
- https://doi.org/10.1080/01457638908939705
Abstract
The thermal hydraulic characteristics of a double-walled tube steam generator designed for sodium-cooled nuclear reactors are presented. The double-walled tube construction, along with double-barrier welds for tube-to-tubesheet joints, virtually eliminates the probability of heat transfer tube failure. Considerations are given to the use of the internal core tube, helical vane swirl generator, external protector tube, and variably perforated flow baffles to improve thermal and hydraulic performance of the steam generator. These thermal hydraulic design features with a particular reference to a 432 MW PRISM steam generator are discussed.Keywords
This publication has 7 references indexed in Scilit:
- Uncertainty Analysis of Heat Exchanger Thermal-Hydraulic DesignsHeat Transfer Engineering, 1987
- An Evaluation of the Effect of Twisted-Tape Swirl Generators in Two-Phase Flow Heat ExchangersHeat Transfer Engineering, 1985
- Multidimensional Numerical Modeling of Heat ExchangersJournal of Heat Transfer, 1982
- Thermal modeling of steam generator tubing under CHF-induced temperature oscillationsInternational Journal of Heat and Mass Transfer, 1982
- The Influence of Twisted Tapes in Subcritical, Once-Through Vapor Generators in Counter flowJournal of Heat Transfer, 1974
- Thermal-Hydraulic Performance of a 2 MWt Sodium-Heated, Forced Recirculation Steam Generator ModelJournal of Engineering for Power, 1974
- TURBULENT FLOW IN PIPES, WITH PARTICULAR REFERENCE TO THE TRANSITION REGION BETWEEN THE SMOOTH AND ROUGH PIPE LAWS.Journal of the Institution of Civil Engineers, 1939