Published October 2013
| Version v1
Miscellaneous
Burst Test of Stress Corrosion Cracked Stream Generator Tubes under Internal Pressure
Creators
- 1. Korea Hydro and Nuclear Power Co., Ltd., Daejeon (Korea, Republic of)
- 2. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
Outside diameter stress corrosion cracking (ODSCC) has been observed on steam generator (SG) Alloy 600HTMA tubing during in-service inspection. There is tendency for the cracking to be parallel to the axis of the tube. To prevent ODSCC tube burst due to internal pressure and maintain structural integrity, robust model to estimate burst pressure is required. These models should be validated on the basis of burst test data. This paper presents experimental burst test results with stress corrosion cracked SG tubing. The results were compared with the existing burst pressure models.
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS Fall meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2013 Fall meeting of the KNS
- Dates
- 23-25 Oct 2013
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 45082479
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CRACKING; CRACKS; IN-SERVICE INSPECTION; STEAM GENERATORS; STRESS CORROSION; TUBES; VALIDATION
- Descriptors DEC
- BOILERS; CHEMICAL REACTIONS; CORROSION; DECOMPOSITION; INSPECTION; PYROLYSIS; TESTING; THERMOCHEMICAL PROCESSES; VAPOR GENERATORS
Optional Information
- Notes
- 3 refs, 5 figs