Published January 1976
| Version v1
Journal article
The straight-tube-once-through forced flow steam generator in the BBR reactor
Creators
- 1. Babcock - Brown Boveri Reaktor G.m.b.H., Mannheim (F.R. Germany)
Description
Operating experience from 6 nuclear power stations with straight-tube-once-through forced flow steam generators has shown that on the basis of model experiments and calculations the expected thermodynamic characteristics and dynamic performance are significantly more favourable. This is particularly applicable to the superheating section of the plant. (orig.)
Abstract (German)
Die Betriebserfahrungen aus 6 Kernkraftwerken mit Geradrohr-Zwangdurchlauf-Dampferzeugern haben gezeigt, dass die aufgrund der Modellversuche und Berechnungen erwartete thermohydraulische Eigenschaft und das dynamische Verhalten wesentlich guenstiger ausfielen. Das gilt besonders fuer den Ueberhitzungsanteil. (orig.)Additional details
Additional titles
- Subtitle (English)
- Design and operational experience
- Original title (German)
- Der Geradrohr-Zwangdurchlauf-Dampferzeuger im BBR-Reaktor
- Original subtitle (German)
- Auslegung und bisherige Erfahrung.
Publishing Information
- Journal Title
- VGB Kraftwerkstech.
- Journal Volume
- 56
- Journal Issue
- 1
- Series
- VGB Kraftwerkstech.
- Journal Page Range
- 1-7
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 7257814
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONFIGURATION; PLANNING; PWR TYPE REACTORS; REACTOR OPERATION; STEAM GENERATORS; SUPERHEATERS; THERMODYNAMICS
- Descriptors DEC
- BOILERS; OPERATION; REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 10 figs.; 2 tabs.