Published March 1979 | Version v1
Report Open

Prestressed concrete reactor vessel for the HHT-670 MW(e) demonstration plant. Pt.3. Experimental studies on the behaviour of concrete and liner at high temperature

  • 1. Ecole Polytechnique Federale, Lausanne (Switzerland)

Description

In connection with the HHT PROJECT (Helium High Temperature Reactor), jointly developed in Germany and Switzerland, an extensive test programme is presently being conducted at the Swiss Federal Institute of Technology in Lausanne in order to gain more experimental information about the rheological and technological problems of Prestressed Concrete Reactor Vessels with warm liner. This programme, executed in close collaboration with Bonnard and Gardel, Consulting Engineers Ltd, consists of, at this stage, three essential parts, namely: 1. Tests on the behaviour of the hot concrete layer; 2. Tests on the behaviour of the anchorages; 3. Tests on the behaviour of the liner. In the following text, some details of this test programme are presented

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Additional details

Publishing Information

Imprint Title
Specialists meeting on vessel concepts for gas-cooled reactors Lausanne, Switzerland 23-25 October 1978
Journal Page Range
p. 44-50.
Report number
IWGHTR--2

Conference

Title
Specialists meeting on vessel concepts for gas-cooled reactors.
Dates
23 - 25 Oct 1978.
Place
Lausanne, Switzerland.

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
12619436
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CREEP; HTGR TYPE REACTORS; LINERS; PRESSURE VESSELS; PRESTRESSED CONCRETE; THERMAL STRESSES; THERMAL TESTING
Descriptors DEC
BUILDING MATERIALS; COMPOSITE MATERIALS; CONCRETES; CONTAINERS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MATERIALS TESTING; MECHANICAL PROPERTIES; NONDESTRUCTIVE TESTING; REACTORS; STRESSES; TESTING