Published 1982 | Version v1
Miscellaneous Restricted

Functional systems of a pressurized water reactor

  • 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

Restricted

The record is publicly accessible, but files are restricted to users with access.

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