Browse > Article
http://dx.doi.org/10.3795/KSME-A.2003.27.5.823

New Fracture Toughness Test Method of Zircaloy-4 Nuclear Fuel Cladding  

Oh, Dong-Joon (안동대학교)
Ahn, Sang-Bok (한국원자력연구소 조사재시험시설(IMEF))
Hong, Kwon-Pyo (한국원자력연구소 조사재시험시설(IMEF))
Publication Information
Transactions of the Korean Society of Mechanical Engineers A / v.27, no.5, 2003 , pp. 823-832 More about this Journal
Abstract
To define the causes of cladding degradation which can take place during the operation of nuclear power plants, it is required to develop the new fracture toughness test of spent fuel cladding. The fracture toughness of Zircaloy-4 cladding was estimated using the recently developed KAERI embedded Charpy (KEC) specimen. Axially notched KEC specimens cut directly from unirradiated fuel claddings, were tested in a way similar to the standard toughness test method of a Single Edge Bending (SEB) specimen. The results of KEC fracture toughness test at room temperatures were discussed and compared with those of the previous other studies. In conclusions, even though the KEC fracture toughness test of nuclear fuel claddings was easier and more reliable than those developed earlier, the results from the cladding fracture tests were not the material characteristics but the specific fracture parameters which were deeply related to the specification of claddings. In addition, the phenomenon of a thickness yielding was not observed from the fracture surface. It was closely related to the fact that the plane strain condition of the KEC specimen was changed to the plane stress condition during crack advancing. It was also supported by the fractographic evidence that the formation of ductile dimples at the crack initiation became the similar appearance such as a quasi-cleavage after the sufficient crack advancing.
Keywords
Nuclear Fuel Cladding; KAERI Embedded Charp(KEC) Specimen; Zircaloy-4 Alloy; IMEF(Irradiated Material Examination Facility);
Citations & Related Records
Times Cited By KSCI : 4  (Citation Analysis)
연도 인용수 순위
1 Ahn, S.B., 2001, 'Development of the Transverse Tensile and Fracture Toughness Test Techniques for Spent Fuel Cladding,' KAERI Research Report KAERI/RR-2156/2000, KAERI, pp. 91-109
2 Grigoriev, V. and Josefsson, B., 1996, 'Fracture Toughness of Zircaloy Cladding Tubes,' Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295, pp. 431-447
3 Edsinger, K., Davies, J.H. and Adamson, R.B., 2000, 'Degraded Fuel Cladding Fractography and Fracture Behavior,' Zirconium in the Nuclear Industry: 12th International Symposium, ASTM STP 1354, pp. 316-339
4 Oh, D.J., Ahn, S.B . and Kim,Y.S., 2001, 'Validation of CCT Fracture Toughness Test with Non-uniformed Pre-fatigue Crack,' Journal of Korean Institute of Metal and Materials, Vol. 39, No. 1, pp. 27-33
5 Buzzard, R.J. Gross, B. and Srawley, J.E., 1978, 'Load-Displacement Measurement and Work Determination in Three-Point Bend Tests of Notched or Precracked Specimens,' Journal of Testing and Evaluation, JTEVA, Vol. 6, No. 1, pp. 35-39   DOI   ScienceOn
6 European Group on Fracture, 1990, 'EGF Recommendations for Determining the Fracture Resistance of Ductile Materials,' EGF P1-90, pp. 9-28
7 Oh, D.J., Ahn, S.B., Kim, Y.S., 2000, 'Fracture Toughness Embrittlement by Hydride in Zr-2.5Nb Pressure Tube,' Proceeding(A) of Korean Society of Mechanical Engineering of 2002 Annual Fall Meeting, Korea University, pp. 93-98   과학기술학회마을
8 Johnson, H.H., 1965, 'Calibrating the Electric Potential Method for Studying Slow Crack Growth,' Materials Research and Standards, pp. 442-445
9 Kim, Y.S., Ahn, S.B., and Kim, J.K., 2001, 'The Strength and Fracture Behavior Characteristics of Irradiated Zr-2.5Nb CANDU Pressure Tube Materials,' Transaction(A) of Korean Society of Mechanical Engineering, Vol. 25, No. 3, pp. 510-519   과학기술학회마을