Published 1981 | Version v1
Book Metadata-only

Control of a PWR plant with straight-tube steam generator

Creators

  • 1. Brown, Boveri und Cie A.G., Mannheim (Germany, F.R.)

Description

In the Muelheim-Kaerlich plant, the first German nuclear steam generation system for a PWR with forced-circulation, straight-tube steam generator and integrated unit control will soon start operation. The paper describes the characteristic features of the BBR plant and control concept. On the basis of simulations, the uncontrolled steady-state behaviour of the steam generator and the control behaviour of the plant are discussed. (orig./GL)

Abstract (German)

Mit der Anlage Muelheim-Kaerlich wird in Deutschland erstmals ein Nukleares Dampferzeugungssystem (NDS) fuer einen Druckwasserreaktor mit Zwangsdurchlauf-Geradrohrdampferzeuger und integrierter Blockregelung in Betrieb gehen. Ziel dieses Vortrages ist die Darstellung der charakteristischen Eigenschaften des BBR-Anlagen- und Regelkonzeptes. Anhand von Simulationsergebnissen wird das ungeregelte Ausgleichsverhalten des Dampferzeugers sowie das Regelverhalten der Gesamtanlage erlaeutert. (orig./GL)

Additional details

Additional titles

Original title (German)
Regelung einer Druckwasserreaktor-Anlage mit Geradrohrdampferzeuger

Publishing Information

Publisher
Fachinformationszentrum Energie, Physik, Mathematik.
Imprint Place
Eggenstein-Leopoldshafen, Germany, F.R.
Imprint Title
Annual meeting on nuclear technology '81 - Reactor conference 1981
Imprint Pagination
668 p.
Journal Page Range
p. 561-564.

Conference

Title
Annual meeting on nuclear technology '81 (JK '81).
Dates
24 - 26 Mar 1981.
Place
Duesseldorf, Germany, F.R.

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
12596561
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CLOSED-LOOP CONTROL; CONTROL SYSTEMS; ECONOMIZERS; FEEDBACK; FEEDWATER; FLOW RATE; FORCED CONVECTION; LOAD MANAGEMENT; MUELHEIM-KAERLICH REACTOR; PRESSURE DEPENDENCE; STEAM GENERATORS; SUBCOOLING; TEMPERATURE DEPENDENCE; TURBOGENERATORS
Descriptors DEC
BOILERS; CONTROL; CONVECTION; COOLING; ELECTRIC GENERATORS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; HYDROGEN COMPOUNDS; MANAGEMENT; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:ISSN 0173-0924.;Jahrestagung Kerntechnik '81 - Reaktortagung 1981.;Tagungsbericht. Sektion 7: Auslegung und Betrieb von kerntechnischen Anlagen.