Published 1977 | Version v1
Report Open

Some problems of the safety of PWR nuclear power plants viewed from the technical standpoint

  • 1. Energoprojekt, Prague (Czechoslovakia)

Description

The paper presents the views of the Czechoslovak design organization on the solution of the technical problems associated with PWR core emergency cooling using pressure accumulators and a system of low-pressure pumps. An analysis is made of the method and the point of inlet of the water to the primary circuit from the accumulators and of the volume and working pressure of the latter. The technical problems of the containment systems in connection with supplementary reactor cooling are discussed. The different types are compared with respect to their functioning, and the requirements which they must fulfil in order to meet the design solution are given. The basic requirements which the design solution must satisfy so as to permit the use of diagnostic methods are also indicated

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Additional titles

Original title (Russian)
Технические соображения по некоторым вопросам безопасности атомных электростанций с реакторами с водой под давлением

Publishing Information

Imprint Pagination
9 p.
Report number
IAEA-CN--36/467

Conference

Title
International conference on nuclear power and its fuel cycles.
Dates
2 - 13 May 1977.
Place
Salzburg, Austria.

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
8303583
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINMENT SYSTEMS; CORE FLOODING SYSTEMS; FUEL ELEMENT FAILURE; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR CORE DISRUPTION; REACTOR SAFETY; RELIABILITY
Descriptors DEC
ACCIDENTS; CONTAINMENT; COOLING SYSTEMS; ECCS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4.1.-.T.2./03.