Published July 2006
| Version v1
Miscellaneous
Development of eddy current technique for components in reactor pressure vessel
Creators
- 1. Hitachi, Ltd., Power and Industrial Systems R and D Laboratory, Hitachi, Ibaraki (Japan)
- 2. Hitachi, Ltd., Hitachi Works, Hitachi, Ibaraki (Japan)
Description
A flexible multi-coil eddy current testing (ECT) probe and a method for measuring the length of flaws have been developed for inspecting complex structures in the reactor pressure vessel of nuclear plants. The probe can be applied to curved surfaces that are larger than a curvature radius of 20 mm. And we propose the method for measuring the flaw length by introducing a decibel drop method of the ECT output signal. From the test results of various EDM notches using the probe and the measuring method, we found that the accuracy of the length sizing was within +/- 3 mm. (author)
Additional details
Additional titles
- Original title (Japanese)
- Nippon hozen gakkai dai-3-kai gakujutsu koenkai yoshishu
Publishing Information
- Imprint Title
- Proceedings of the 3rd annual meeting of Japan Society of Maintenology
- Imprint Pagination
- 405 p.
- Journal Page Range
- p. 350-351
Conference
- Title
- 3. annual meeting of Japan Society of Maintenology
- Dates
- 6-7 Jul 2006
- Place
- Sendai, Miyagi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 42010985
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCURACY; DEFECTS; DISTRIBUTION; EDDY CURRENTS; ELECTRIC DISCHARGES; ELECTRIC POTENTIAL; LENGTH; MACHINING; NUCLEAR POWER PLANTS; PROBES; REACTOR COMPONENTS; SIZE
- Descriptors DEC
- CURRENTS; DIMENSIONS; ELECTRIC CURRENTS; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS
Optional Information
- Notes
- 2 refs., 4 figs. Imprint:Nippon hozen gakkai dai-3-kai gakujutsu koenkai yoshishu