Published 1976 | Version v1
Report Restricted

Fundamentals of pressurized water reactors. Pt. 2

Creators

Description

The nuclear steam supply system (NSSS) of a pressurized water reactor mainly consists of the reactor pressure vessel with the nuclear heat source, the pressurizer, coolant piping, reactor coolant pumps and steam generators. Depending on deliverer, performance data and type of the used components, the design of a NSSS may differ in the number of reactor coolant loops. The here discussed NSSS is a so called 'two loop arrangement' with once-through steam generator (OTSG). (orig.)

Abstract (German)

Das Dampfversorgungssystem (NSSS) eines Druckwasserreaktors besteht im wesentlichen aus dem Reaktordruckbehaelter mit nuklearer Waermequelle, dem Druckhalter, der Kuehlmittelleitung, den Kuehlmittelpumpen und den Dampferzeugern. Je nach Hersteller, Betriebsverhalten und Art der Komponenten kann die Zahl der Kuehlkreislaeufe des NSSS unterschiedlich sein. Bei dem hier beschriebenen NSSS handelt es sich um eine sogenannte 'two-loop' Anordnung mit Durchlauf-Dampferzeuger (OTSG). (orig.)

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Additional details

Additional titles

Subtitle (English)
NSSS with once through steam generators

Publishing Information

Imprint Pagination
25 p.
Report number
AED-Conf--76-660-019

Conference

Title
IAEA international training course on nuclear power project planning and implementation.
Dates
6 Sep 1976.
Place
Karlsruhe, Germany, F.R.

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
8322306
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONSTRUCTION; DIAGRAMS; PERFORMANCE; PRESSURE VESSELS; PRESSURIZERS; PWR TYPE REACTORS; REACTOR CONTROL SYSTEMS; REACTOR CORES
Descriptors DEC
CONTAINERS; CONTROL SYSTEMS; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
36 figs.