Published 1977
| Version v1
Report
Restricted
Thermal shock studies associated with injection of emergency core coolant in pressurized water reactors
Description
Studies to determine the accuracy of calculational techniques for predicting crack initiation and arrest in PWR vessels due to thermal shock from ECC injection are described. The reference calculational model is reviewed, the experimental program and facilities are described, and some thermal shock experiments and results are discussed
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- CONF-770807--29
Conference
- Title
- 4. international conference on structural mechanics in reactor technology.
- Dates
- 15 - 19 Aug 1977.
- Place
- San Francisco, California, United States of America (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9357745
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACKS; ECCS; FRACTURE PROPERTIES; LOSS OF COOLANT; PRESSURE VESSELS; PWR TYPE REACTORS; SPATIAL DISTRIBUTION; STRESSES; THERMAL SHOCK
- Descriptors DEC
- ACCIDENTS; CONTAINERS; DISTRIBUTION; MECHANICAL PROPERTIES; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS