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Volumn , Issue 1467, 2005, Pages 851-872

Mechanical properties of zircaloy-4 PWR fuel cladding with burnup 54-64MWd/kgU and implications for RIA behavior

Author keywords

CABRI; Embrittlement; High burnup; Hydride; Irradiated; Mechanical properties; PROMETRA; REP Na; RIA; Zircaloy 4

Indexed keywords

ACCIDENTS; EMBRITTLEMENT; HYDRIDES; IRRADIATION; NUCLEAR FUELS; SPALLING; STRAIN; TENSILE TESTING; THICKNESS MEASUREMENT; TRANSIENTS;

EID: 33744908046     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (14)

References (16)
  • 6
    • 0032310347 scopus 로고    scopus 로고
    • Failure of the zircaloy cladding under transverse plane-strain deformation
    • Link, T. M., Koss, D. A. and Motta, A. T., "Failure of the Zircaloy Cladding under Transverse Plane-Strain Deformation," Nuclear Engineering and Design, Vol. 186, pp. 379-394, 1998.
    • (1998) Nuclear Engineering and Design , vol.186 , pp. 379-394
    • Link, T.M.1    Koss, D.A.2    Motta, A.T.3
  • 7
    • 5544310313 scopus 로고    scopus 로고
    • Effects of hydride precipitate localization and neutron fluence on the ductility of irradiated zircaloy-4
    • E. R. Bradley and G. P. Sabol, Eds., ASTM International, West Conshohocken, PA
    • Garde, A. M., Smith, G. P., and Pirek, R. C., "Effects of Hydride Precipitate Localization and Neutron Fluence on the Ductility of Irradiated Zircaloy-4," Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295, E. R. Bradley and G. P. Sabol, Eds., ASTM International, West Conshohocken, PA, 1996, pp. 407-430.
    • (1996) Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP , vol.1295 , pp. 407-430
    • Garde, A.M.1    Smith, G.P.2    Pirek, R.C.3
  • 9
    • 0030287457 scopus 로고    scopus 로고
    • Detrimental role of hydrogen on the corrosion rate of zirconium alloys
    • E. R. Bradley and G. P. Sabol, Eds., ASTM International, West Conshohocken, PA
    • Blat, M. and Noel, D., "Detrimental Role of Hydrogen on the Corrosion Rate of Zirconium Alloys," Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295, E. R. Bradley and G. P. Sabol, Eds., ASTM International, West Conshohocken, PA, 1996, pp. 319-337.
    • (1996) Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP , vol.1295 , pp. 319-337
    • Blat, M.1    Noel, D.2
  • 10
    • 0042784199 scopus 로고    scopus 로고
    • The influence of hydride blisters on the fracture of zircaloy-4
    • Pierron, O. N., Koss, D. A., Motta, A. T., and Chan, K. S., "The Influence of Hydride Blisters on the Fracture of Zircaloy-4," Journal of Nuclear Materials, Vol. 322, 2003, pp. 21-35.
    • (2003) Journal of Nuclear Materials , vol.322 , pp. 21-35
    • Pierron, O.N.1    Koss, D.A.2    Motta, A.T.3    Chan, K.S.4
  • 13
    • 0022043251 scopus 로고
    • The influence of multiaxial state of stress on the hydrogen embrittlement of zirconium alloy sheet
    • Yunchang, F. and Koss, D. A., "The Influence of Multiaxial State of Stress on the Hydrogen Embrittlement of Zirconium Alloy Sheet," Metallurgical Transaction A, Vol. 16A, 1985, pp. 675-681.
    • (1985) Metallurgical Transaction A , vol.16 A , pp. 675-681
    • Yunchang, F.1    Koss, D.A.2
  • 14
    • 0036506482 scopus 로고    scopus 로고
    • Assessment of the combined effects of irradiation and hydrogenation on the fracture behavior of zircaloy fuel claddings by fracture mechanics
    • Kuroda, M. and Yamanaka, S., "Assessment of the Combined Effects of Irradiation and Hydrogenation on the Fracture Behavior of Zircaloy Fuel Claddings by Fracture Mechanics," Journal of Nuclear Science and Technology, Vol. 39, 2002, pp. 234-240.
    • (2002) Journal of Nuclear Science and Technology , vol.39 , pp. 234-240
    • Kuroda, M.1    Yamanaka, S.2
  • 15
    • 0035127975 scopus 로고    scopus 로고
    • Analysis of the fracture behavior of hydrided fuel cladding by fracture mechanics
    • Kuroda, M., Yamanaka, S., Nagase, F., and Uetsuka, H., "Analysis of the Fracture Behavior of Hydrided Fuel Cladding by Fracture Mechanics," Nuclear Engineering and Design, Vol. 203, 2001, pp. 185-194.
    • (2001) Nuclear Engineering and Design , vol.203 , pp. 185-194
    • Kuroda, M.1    Yamanaka, S.2    Nagase, F.3    Uetsuka, H.4


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.