Published January 1985
| Version v1
Journal article
An examination of experimental programmes to assess the influence of material toughness on vessel integrity during PTS
Creators
- 1. Stuttgart Univ. (Germany, F.R.). Staatliche Materialpruefungsanstalt
- 2. Oak Ridge National Lab., TN (USA)
Description
Three extensive experimental and analytical programmes are underway at the HDR, the MPA and ORNL, whose aim is to investigate fracture mechanics phenomena parameters. The quantification of these parameters is important for a fuller assessment of the safety margins in the pressure boundary of a nuclear reactor system in the event of occurrence of a pressurized thermal shock (PTS) accident. The three programmes are reviewed and it is shown that between the three, a full range of material properties is adequately covered. (orig.)
Additional details
Publishing Information
- Journal Title
- Nucl. Eng. Des.
- Journal Volume
- 84
- Journal Issue
- 2
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 201-211
- ISSN
- 0029-5493
- CODEN
- NEDEA
Conference
- Title
- 9. MPA seminar on fracture prevention and availability.
- Dates
- 13-14 Oct 1983.
- Place
- Stuttgart (Germany, F.R.).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 17040511
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CRACKS; FEDERAL REPUBLIC OF GERMANY; FRACTURE MECHANICS; FRACTURE PROPERTIES; HDR REACTOR; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR OPERATION; REACTOR SAFETY EXPERIMENTS; THERMAL SHOCK; TRANSIENTS; USA
- Descriptors DEC
- ACCIDENTS; CONTAINERS; COOLING SYSTEMS; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; EUROPE; EXPERIMENTAL REACTORS; MECHANICAL PROPERTIES; MECHANICS; NORTH AMERICA; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS