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
Creators
- 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
Files
12619436.pdf
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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