Development of an ECT technique for discriminating between a through-wall/non through-wall crack in a steam generator tube
Creators
- 1. Korea Atomic Energy Research Inst., Daejon (Korea, Republic of)
- 2. Seoul National Univ., Seoul (Korea, Republic of)
Description
In a lot of pressurized water reactors, PWSCC (primary water stress corrosion cracking) has been observed in the expansion or u-bend transitions of the alloy 600 steam generator tubes. Particularly, the development of a through-wall crack may cause leakage of the primary coolant during operation and the resultant forced outage, and the in-situ pressure test has often been used to evaluate the integrity and the leakage of the cracked tube during an in-service inspection. However, this process requires additional equipment and hours, and the tested tubes are plugged due to the plastic deformation induced by the internal pressurization. This paper describes a new evaluation technique of the Eddy current test, by which it can be determined whether the crack is through-wall or non through-wall. The technique is based upon the analysis of the characteristics in the Eddy current signals from the crack and also includes the method of measuring exact through-wall length of the crack. The proof and applicability of the technique is discussed with the results of the destructive tests on cracked tubes extracted from a commercial power plant. Also, the effect of crack opening, which reflects the driving force for a crack propagation of non through-wall crack and the leak rate of a through-wall crack, upon the characteristics of the Eddy current signals from the coils of the motorized rotating probe is investigated and discussed using steam generator tube samples with manufactured axial cracks of a through-wall and non through-wall. (orig.)
Additional details
Publishing Information
- Journal Title
- Key Engineering Materials
- Journal Volume
- 270-273
- Journal Issue
- pt.1
- Series
- Advances in nondestructive evaluation
- Journal Page Range
- p. 600-605
- ISSN
- 1013-9826
- CODEN
- KEMAEY
Conference
- Title
- 11. Asia-Pacific conference on non-destructive testing
- Acronym
- APCNDT-11
- Dates
- 3-7 Nov 2003
- Place
- Jeju Island (Korea, Republic of)
INIS
- Country of Publication
- Switzerland
- Country of Input or Organization
- Switzerland
- INIS RN
- 36000044
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACK PROPAGATION; CRACKS; EDDY CURRENT TESTING; INCONEL 600; NOTCHES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; STEAM GENERATORS; STRESS CORROSION; TUBES; WATER
- Descriptors DEC
- ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; BOILERS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; ELECTROMAGNETIC TESTING; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HYDROGEN COMPOUNDS; INCONEL ALLOYS; IRON ALLOYS; MATERIALS; MATERIALS TESTING; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; NONDESTRUCTIVE TESTING; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TESTING; THERMAL REACTORS; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS