Published 1981
| Version v1
Journal article
Fatigue crack growth in pressurized water reactor feedwater lines
Description
In mid-1979 cracking was discovered in one of the feedwater lines of an operting PWR system. Further inspection of the other lines at this plant, as well as other plants, revealed other instances of cracking, and as a result an exhaustive investigation was undertaken. This paper will present a review of the investigation, with emphasis on the use of field measurements, flow model tests and metallurgical investigations to predict both the initiation and growth of these cracks. 12 refs
Additional details
Publishing Information
- Journal Title
- Am. Soc. Mech. Eng., [Pap.]
- Journal Issue
- 81-pvp-2
- Series
- Am. Soc. Mech. Eng., [Pap.].
- ISSN
- 0402-1215
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13684624
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- CRACK PROPAGATION; FATIGUE; FEEDWATER; NUCLEAR POWER PLANTS; PIPES; PWR TYPE REACTORS; STEELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; OXYGEN COMPOUNDS; POWER PLANTS; REACTORS; THERMAL POWER PLANTS; TRANSITION ELEMENT ALLOYS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS