Published 2007
| Version v1
Miscellaneous
The use of eddy current testing for nuclear fuel rods cladding evaluation
- 1. Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)
Description
Nuclear fuel rods cladding must be tested after their manufacture and during their operational life. This paper describes a study about the use of eddy current test method as a nondestructive tool for nuclear fuel rods cladding evaluation. The experiments were carried out using two different probes: an external probe and an internal probe. The main goal was to verify the sensitivity of the eddy current test system, to develop calibration and reference standards and to establish the main capabilities and limitations presented by this test method for this application. (author)
Additional details
Publishing Information
- ISBN
- 978-85-99141-02-1
- Imprint Title
- Proceedings of the INAC 2007 International nuclear atlantic conference. Nuclear energy and energetic challenges for 21st. century. 15. Brazilian national meeting on reactor physics and thermal hydraulics; 8. Brazilian national meeting on nuclear applications
- Imprint Pagination
- [vp.]
- Journal Page Range
- [7 p.]
Conference
- Title
- INAC 2007 International nuclear atlantic conference. Nuclear energy and energetic challenges for 21st. century. 15. Brazilian national meeting on reactor physics and thermal hydraulics; 8. Brazilian national meeting on nuclear applications
- Dates
- 30 Sep - 5 Oct 2007
- Place
- Santos, SP (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 39093818
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature
- Descriptors DEI
- CALIBRATION STANDARDS; CLADDING; EDDY CURRENT TESTING; EXPERIMENTAL DATA; FUEL RODS; SENSITIVITY; THICKNESS; ZIRCALOY 4
- Descriptors DEC
- ALLOY-ZR98SN-4; ALLOYS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DATA; DEPOSITION; DIMENSIONS; ELECTROMAGNETIC TESTING; FUEL ELEMENTS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INFORMATION; IRON ADDITIONS; IRON ALLOYS; MATERIALS; MATERIALS TESTING; NONDESTRUCTIVE TESTING; NUMERICAL DATA; REACTOR COMPONENTS; STANDARDS; SURFACE COATING; TESTING; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 5 refs., 6 figs., 2 tabs. Code: R08_1851.pdf