Published 1982
| Version v1
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Functional systems of a pressurized water reactor
Creators
- 1. Karlsruhe Univ. (T.H.) (Germany, F.R.)
Description
The main topics, discussed in the present paper, are: - Principle design of the reactor coolant system - reactor pressure vessel with internals - containment design - residual heat removal and emergency cooling systems - nuclear component cooling systems - emergency feed water systems - plant electric power supply system. (orig./RW)
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Publishing Information
- Imprint Pagination
- 23 p.
- Report number
- INIS-mf--7945
Conference
- Title
- IAEA interregional training course on 'instrumentation and control of nuclear power plants'.
- Dates
- 11 Oct - 17 Nov 1982.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 14746845
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REVIEWS
- Descriptors DEC
- CONTAINERS; COOLING SYSTEMS; DOCUMENT TYPES; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS