Experimental verification of the horizontal steam generator boil-off transfer degradation at natural circulation
Creators
- 1. Finnish Centre for Radiation and Nuclear Safety, Helsinki (Finland)
- 2. VTT Energy, Lappeenranta (Finland)
Description
The presentation summarises the highlights of experimental results obtained for VVER type horizontal steam generator heat transfer, primary side flow pattern, and mixing in the hot collector during secondary side boil-off with primary at single-phase natural circulation. The experiments were performed using the PACTEL facility with Large Diameter (LD) steam generator models, with collector instrumentation designed specifically for these tests. The key findings are as follows: (1) the primary to secondary heat transfer degrades as the secondary water inventory is depleted, following closely the wetted tube area; (2) a circulatory flow pattern exists in the tube bundle, resulting in reversed flow (from cold to the hot collector) in the lower part of the tube bundle, and continuous flow through the upper part, including the tubes that have already dried out; and (3) mixing of the hot leg flow entering the hot collector and reversed, cold, tube flow remains confined within the collector itself, extending only a row or two above the elevation at which tube flow reversal has taken place
Files
Additional details
Publishing Information
- ISBN
- 951-764-189-3
- Imprint Title
- Fourth international seminar on horizontal steam generators
- Imprint Pagination
- 305 p.
- Journal Page Range
- p. 1-14.
- Report number
- LTKK-TJ--67
Conference
- Title
- 4. international seminar on horizontal steam generators.
- Dates
- 11-13 Mar 1997.
- Place
- Lappeenranta (Finland).
INIS
- Country of Publication
- Finland
- Country of Input or Organization
- Finland
- INIS RN
- 29024673
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- EXPERIMENTAL DATA; FLUID FLOW; HEAT TRANSFER; NATURAL CONVECTION; PRIMARY COOLANT CIRCUITS; SECONDARY COOLANT CIRCUITS; STEAM GENERATORS; TEST FACILITIES; WWER TYPE REACTORS
- Descriptors DEC
- BOILERS; CONVECTION; COOLING SYSTEMS; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 6 refs.