Experimental results from a test performed on the T-joint to pressurizer of WWER 440 type 213 NPP
Description
A test was conducted on a T-joint used in the primary coolant loop. The T-joint was a replica of that between the surge line (connected to the pressurizer) and the primary coolant loop. The test was carried out in 2 stages, designed to simulate a specific reactor event and to determine the failure load. During the first stage, the experimental vessel was held at the normal operating temperature (about 300 degC) and pressure (12.5 MPa), and a force was applied to the branch to simulate the bending moment during the event. The vessel was depressurized for the second stage test, and the bending moment was applied until the limiting load was reached. The stability of the component was demonstrated in both stages of the experiment. In the second stage, ductile tearing was observed to a large extent
Availability note (English)
Available from Nuclear Research Institute Rez, 250 68 Rez, Czech Republic.Additional details
Publishing Information
- Imprint Pagination
- [16 p.].
- Report number
- UJV--10668-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 29006832
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BENDING; CRACK PROPAGATION; CRACKS; DYNAMIC LOADS; MECHANICAL TESTS; PIPE FITTINGS; PIPE JOINTS; PRIMARY COOLANT CIRCUITS; STATIC LOADS; WWER TYPE REACTORS
- Descriptors DEC
- COOLING SYSTEMS; DEFORMATION; ENRICHED URANIUM REACTORS; JOINTS; MATERIALS TESTING; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 12 figs.