Published 1976
| Version v1
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Fundamentals of pressurized water reactors. Pt. 2
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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.