Published April 1985
| Version v1
Journal article
Measuring dynamic displacement inside a reactor pressure vessel at 3100C and 110 bar
Creators
Description
In a research project sponsored by the West German Government, critical components of light-water nuclear reactors are being rigidly tested. One series of tests simulates a rupture in the primary-coolant circuit and measures the effect of resulting loads on the reactor pressure vessel and its internals. The displacement transducers used in the test are capable of very precise measurement despite extraordinarily high pressure and temperature conditions inside the pressure vessel. (orig.)
Additional details
Publishing Information
- Journal Title
- Rep. Appl. Meas.
- Journal Volume
- 1
- Journal Issue
- 1
- Series
- Rep. Appl. Meas.
- Journal Page Range
- 5-8
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 17036651
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONTAINMENT BUILDINGS; DEPRESSURIZATION; DISPLACEMENT GAGES; HDR REACTOR; PRESSURE VESSELS; SHOCK WAVES; TEMPERATURE MEASUREMENT; TRANSDUCERS
- Descriptors DEC
- BUILDINGS; BWR TYPE REACTORS; CONTAINERS; CONTAINMENT; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; MEASURING INSTRUMENTS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS