Measurement of residual stress in fuel cladding tubes by x-ray method
Creators
- 1. Toshiba Corp., Kawasaki, Kanagawa (Japan). Research and Development Center
Description
It is difficult to predict the residual stress distribution in FBR or LWR fuel cladding tubes using computer code or mechanical methods. In order to measure these stresses by X-ray method, the characterization of X-ray diffraction and optimum condition for stress measurement are investigated. Following conclusions are obtained: (1) The (211) CrKα and (213-3) CuKα reflections are most suitable for the stress analysis of 316 stainless steel and Zircaloy-2 fuel cladding tubes, respectively. (2) Comparison between strain measured by X-ray and strain measured by strain gage shows good agreement in elastic region for both materials. (3) In order to obtain accurate results, it needs to remove surface more than 3 μm by electropolishing or acid etching. (4) There exists compressive residual stress in typical FBR fuel cladding tubes, and TIG welding of end plug induces additional compressive stress in welded portion or heat affected zone. (5) Residual stress distributions in Zircaloy-2 cladding tube deformed locally by the out-of-pile simulation tests, are obtained by the application of X-ray method. (author)
Availability note (English)
Available from DOI: https://doi.org/10.3327/jaesj.22.580Additional details
Additional titles
- Original title (Japanese)
- X線による燃料被覆管の残留応力測定
Identifiers
- DOI
- 10.3327/jaesj.22.580;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 22
- Journal Issue
- 8
- Journal Page Range
- p. 580-589
- ISSN
- 0004-7120
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 53113935
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCURACY; DEFORMATION; FBR TYPE REACTORS; FUEL CANS; MATERIALS TESTING; MECHANICAL PROPERTIES; RESIDUAL STRESSES; STAINLESS STEEL-316; WATER COOLED REACTORS; WELDING; X-RAY DIFFRACTION; ZIRCALOY 2
- Descriptors DEC
- ALLOYS; ALLOY-ZR98SN-2; AUSTENITIC STEELS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; COHERENT SCATTERING; CORROSION RESISTANT ALLOYS; DIFFRACTION; EPITHERMAL REACTORS; FABRICATION; FAST REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ADDITIONS; IRON ALLOYS; IRON BASE ALLOYS; JOINING; MATERIALS; MOLYBDENUM ALLOYS; NICKEL ADDITIONS; NICKEL ALLOYS; REACTORS; SCATTERING; STAINLESS STEELS; STEEL-CR17NI12MO3; STEELS; STRESSES; TESTING; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 9309120; This record replaces 12635656