Consequences of 'hot spots' on PCRVs
Creators
- 1. Hochtemperatur-Reaktorbau G.m.b.H., Mannheim (Germany, F.R.)
Description
The concrete walls of the PCRVs shall be protected from the high temperatures of the reactors coolant by means of the heat protection system, i.e. insulation and cooling. For large areas of the inside face of the vessel, the concrete temperatures generally lie thetween 400C to 700C. Should the insulation be damaged, the above temperatures could be greatly exceeded, depending on the extent of the damage and the effectiveness of the cooling system. Although the method of fixing the insulation to the liner is more than adequate, a constant check is to be kept of the insulation effectiveness. The cooling system lends itself to such a check. A deterioration in the insulation would result automatically in an additional rise in temperature of the cooling water. By checking the cooling water at entry and exit with thermometers and feeding this information to a simpe computer, temperature changes in the cooling water of about 10C and above can be detected with certainty. This temperature rise of about 10C corresponds to an area of completely damaged insulation of less than 1 m2 up to a few m2 depending on the prevailing thermal conditions. It can be generally concluded from calculations on the THTR-300 reactor that because of the constant check on the liner cooling system, all damage to the insulation which could impair the PCRV integrity can be detected. (Auth.)
Additional details
Additional titles
- Original title (German)
- Auswirkungen von heissenbereichen auf Spannbeton behaelter
Publishing Information
- Publisher
- North-Holland.
- Imprint Place
- Amsterdam, The Netherlands
- Imprint Title
- Structural mechanics in reactor technology
- Imprint Pagination
- v. 3 p. H3/7 1-8.
Conference
- Title
- 3. international conference on structural mechanics in reactor technology.
- Dates
- 1 Sep 1975.
- Place
- London, UK.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 8287390
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLANTS; CRACKS; CREEP; FAILURES; HIGH TEMPERATURE; HOT SPOTS; INSPECTION; PRESTRESSED CONCRETE; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR OPERATION; REACTOR SAFETY; REACTOR SHUTDOWN; REACTOR VESSELS; SHRINKAGE; STRAINS; STRESSES; TEMPERATURE DEPENDENCE; TEMPERATURE MEASUREMENT; THERMAL EXPANSION; THERMAL INSULATION; THTR-300 REACTOR; TRANSIENTS; YOUNG MODULUS
- Descriptors DEC
- BUILDING MATERIALS; CONCRETES; CONTAINERS; COOLING SYSTEMS; ELASTICITY; ENRICHED URANIUM REACTORS; EXPANSION; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HOMOGENEOUS REACTORS; HTGR TYPE REACTORS; MECHANICAL PROPERTIES; OPERATION; PEBBLE BED REACTORS; POWER REACTORS; REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; TENSILE PROPERTIES; THERMAL REACTORS; THORIUM REACTORS