HTGR Knowledge Base
Conference Article: Thermohydraulic verification during THTR steam generator commissioning
Henry, C. (Sulzer Brothers Ltd., Winterthur (Switzerland)); Elter, C. (Hochtemperatur-Reaktorbau GmbH, Mannheim (Germany))Abstract
In one of the six THTR 300 steam generators thermocouples are installed inside the heat transfer tube bundles for measuring the gas and steam temperatures. Fluid temperature distribution measurements along and across the helix bundle have been recorded in its first months of operation over a load range of 40% up to 100% for steady state and transient conditions. Using these measurements as well as the rest of the operating instrumentation. the computer programs for the design of heat exchanger heat transfer areas are verified. The temperature measurements for steady state conditions are compared with predictions obtained in the design stage. In these codes. the heat transferred from the outside helium gas to the water/steam inside the tubes is determined in discrete steps along the heating surface by one- and two-phase heat transfer correlations. The degree of conformity between prediction and measurement is discussed and compared with more recent correlations.
view the full text of this article (7 pages, format: PDF, size= 1123kB)
key words: Gas Cooled Reactor, Nuclear Technology
- Reference:
- Specialists' meeting on technology of steam generators for gas-cooled reactors Winterthur (Switzerland) 9-12 Mar 1987
- International Atomic Energy Agency, International Working Group on Gas-Cooled Reactors, Vienna (Austria)
- IWGGCR--15, pp:204-210
- International Atomic Energy Agency, International Working Group on Gas-Cooled Reactors, Vienna (Austria)
