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Volumn 228, Issue 1-3, 2004, Pages 3-13

Short-term rupture studies of Zircaloy-4 and Nb-modified Zircaloy-4 tubing using closed-end internal pressurization

Author keywords

[No Author keywords available]

Indexed keywords

CREEP; DILATOMETERS; EXTRAPOLATION; GRAIN SIZE AND SHAPE; NIOBIUM; NUCLEAR REACTORS; PRESSURIZATION; SPENT FUELS; STRAIN; STRESSES; TUBING; VISCOSITY; WETTING;

EID: 0442311884     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2003.06.013     Document Type: Conference Paper
Times cited : (32)

References (33)
  • 1
    • 40849143392 scopus 로고
    • A first report on deformation mechanism maps
    • Ashby, M.F., 1972. A first report on deformation mechanism maps. Acta Met. 20, 887-894; Frost, H.J., Ashby, M.F., 1982. Deformation Mechanism Maps. Pergamon Press, Oxford.
    • (1972) Acta Met. , vol.20 , pp. 887-894
    • Ashby, M.F.1
  • 2
    • 40849143392 scopus 로고
    • Pergamon Press, Oxford
    • Ashby, M.F., 1972. A first report on deformation mechanism maps. Acta Met. 20, 887-894; Frost, H.J., Ashby, M.F., 1982. Deformation Mechanism Maps. Pergamon Press, Oxford.
    • (1982) Deformation Mechanism Maps
    • Frost, H.J.1    Ashby, M.F.2
  • 3
    • 85168710739 scopus 로고
    • In-reactor deformation of Zr-2.5 wt.% Nb pressure tubes
    • Influence of Radiation on Material Properties: Proceedings of the 13th International Symposium (Part II)
    • Causey, A.R., Fidleris, V., MacEwen, S.R., Schulte, C.W., 1987. In-reactor deformation of Zr-2.5 wt.% Nb pressure tubes. In: Influence of Radiation on Material Properties: Proceedings of the 13th International Symposium (Part II). ASTM STP 956, pp. 54-68.
    • (1987) ASTM STP , vol.956 , pp. 54-68
    • Causey, A.R.1    Fidleris, V.2    Macewen, S.R.3    Schulte, C.W.4
  • 4
    • 0024640221 scopus 로고
    • Prediction of maximum allowable temperature for dry storage of Zircaloy-clad spent fuel in inert atmosphere
    • Chin B.A., Gilbert E.R. Prediction of maximum allowable temperature for dry storage of Zircaloy-clad spent fuel in inert atmosphere. Nucl. Tech. 85:1989;57-65.
    • (1989) Nucl. Tech. , vol.85 , pp. 57-65
    • Chin, B.A.1    Gilbert, E.R.2
  • 5
    • 0024087716 scopus 로고
    • The irradiation creep and growth phenomena
    • Fidleris V. The irradiation creep and growth phenomena. J. Nucl. Mater. 159:1988;22-42.
    • (1988) J. Nucl. Mater. , vol.159 , pp. 22-42
    • Fidleris, V.1
  • 6
    • 0018466133 scopus 로고
    • Creep damage in Zircaloy-4 at LWR temperatures
    • Keusseyan R.L., Hu C.P., Li C.Y. Creep damage in Zircaloy-4 at LWR temperatures. J. Nucl. Mater. 80:1979;390-392.
    • (1979) J. Nucl. Mater. , vol.80 , pp. 390-392
    • Keusseyan, R.L.1    Hu, C.P.2    Li, C.Y.3
  • 7
    • 0016498226 scopus 로고
    • Deformation mechanism mapping of α-Zr and Zirclaloy-2
    • Knorr D.B., Notis M.R. Deformation mechanism mapping of α-Zr and Zirclaloy-2. J. Nucl. Mater. 56:1975;18-23.
    • (1975) J. Nucl. Mater. , vol.56 , pp. 18-23
    • Knorr, D.B.1    Notis, M.R.2
  • 8
    • 5544252605 scopus 로고    scopus 로고
    • A model for analysis of the effect of final annealing on the in- and out-reactor creep behavior of Zircaloy cladding
    • Zirconium in the Nuclear Industry: Proceedings of the Eleventh International Symposium
    • Limback, M., Andersson, T., 1996. A model for analysis of the effect of final annealing on the in- and out-reactor creep behavior of Zircaloy cladding. In: Zirconium in the Nuclear Industry: Proceedings of the Eleventh International Symposium. ASTM STP 1295, pp. 448-468.
    • (1996) ASTM STP , vol.1295 , pp. 448-468
    • Limback, M.1    Andersson, T.2
  • 9
  • 10
    • 0025429818 scopus 로고
    • Creep deformation of an unirradiated Zircaloy-4 nuclear fuel cladding tube under dry storage conditions
    • Mayuzumi M., Onchi T. Creep deformation of an unirradiated Zircaloy-4 nuclear fuel cladding tube under dry storage conditions. J. Nucl. Mater. 171:1990;381-388.
    • (1990) J. Nucl. Mater. , vol.171 , pp. 381-388
    • Mayuzumi, M.1    Onchi, T.2
  • 11
    • 0026128940 scopus 로고
    • A method to evaluate the maximum allowable temperature of spent fuel in dry storage during a postulated accident
    • Mayuzumi M., Onchi T. A method to evaluate the maximum allowable temperature of spent fuel in dry storage during a postulated accident. Nucl. Tech. 93:1991;382-388.
    • (1991) Nucl. Tech. , vol.93 , pp. 382-388
    • Mayuzumi, M.1    Onchi, T.2
  • 12
    • 0015661928 scopus 로고
    • Transitional creep mechanisms in Al-5Mg at high stresses
    • Murty K.L. Transitional creep mechanisms in Al-5Mg at high stresses. Scripta Met. 7:1973;899-902.
    • (1973) Scripta Met. , vol.7 , pp. 899-902
    • Murty, K.L.1
  • 13
    • 0010709636 scopus 로고
    • Biaxial creep of Zircaloy cladding
    • Murty K.L. Biaxial creep of Zircaloy cladding. Trans. IIM. 39:1986;357-368.
    • (1986) Trans. IIM , vol.39 , pp. 357-368
    • Murty, K.L.1
  • 14
    • 0001655045 scopus 로고
    • Dislocation jump distances during creep of pure and doped NaCl single crystals using nuclear magnetic resonance pulse techniques
    • Murty K.L., Kanert O. Dislocation jump distances during creep of pure and doped NaCl single crystals using nuclear magnetic resonance pulse techniques. J. Appl. Phys. 67:1990;2866-2872.
    • (1990) J. Appl. Phys. , vol.67 , pp. 2866-2872
    • Murty, K.L.1    Kanert, O.2
  • 16
    • 0002233595 scopus 로고    scopus 로고
    • Stress corrosion cracking and pellet cladding mechanical interaction of Zircaloys - Application to LWRs
    • Khanna, A.S., Sharma, K.S., Sinha, A.K. (Eds.). Academic Books International, New Delhi
    • Murty, K.L., 1999. Stress corrosion cracking and pellet cladding mechanical interaction of Zircaloys - application to LWRs. In: Khanna, A.S., Sharma, K.S., Sinha, A.K. (Eds.), Emerging Trends in Corrosion Control - Evaluation, Monitoring and Solutions. Academic Books International, New Delhi, pp. 702-710.
    • (1999) Emerging Trends in Corrosion Control - Evaluation, Monitoring and Solutions , pp. 702-710
    • Murty, K.L.1
  • 17
    • 0442320687 scopus 로고    scopus 로고
    • Internal pressurization creep of thin-walled tubing of Zr-alloys for dry storage feasibility of nuclear spent fuel
    • Murty, K.L., 2000. Internal pressurization creep of thin-walled tubing of Zr-alloys for dry storage feasibility of nuclear spent fuel. J. Metals, pp. 34-38.
    • (2000) J. Metals , pp. 34-38
    • Murty, K.L.1
  • 20
    • 0029632958 scopus 로고
    • Transitions in creep mechanisms and creep anisotropy in a Zr-1Nb-1Sn-0.2Fe sheet
    • Murty, K.L., Ravi, J., Wiratmo, 1995. Transitions in creep mechanisms and creep anisotropy in a Zr-1Nb-1Sn-0.2Fe sheet. Nucl. Eng. Design, 156, pp. 359-371.
    • (1995) Nucl. Eng. Design , vol.156 , pp. 359-371
    • Murty, K.L.1    Ravi, J.2    Wiratmo3
  • 21
    • 0022660297 scopus 로고
    • LWR spent fuel storage behavior
    • Peehs M., Fleisch J. LWR spent fuel storage behavior. J. Nucl. Mater. 137:1986;190-202.
    • (1986) J. Nucl. Mater. , vol.137 , pp. 190-202
    • Peehs, M.1    Fleisch, J.2
  • 23
    • 0010704004 scopus 로고
    • Temperature limit determination for the inert dry storage of spent nuclear fuel
    • Pescatore, C., Cowgill, M.G., 1994. Temperature limit determination for the inert dry storage of spent nuclear fuel. EPRI Report TR-103949.
    • (1994) EPRI Report , vol.TR-103949
    • Pescatore, C.1    Cowgill, M.G.2
  • 25
    • 0016521350 scopus 로고
    • Intergranular fracture at elevated temperature
    • Raj R., Ashby M.F. Intergranular fracture at elevated temperature. Acta Met. 23:1975;653-667.
    • (1975) Acta Met. , vol.23 , pp. 653-667
    • Raj, R.1    Ashby, M.F.2
  • 26
    • 0028446989 scopus 로고
    • Effects of recrystallization and Nb-additions on texture and mechanical anisotropy of Zircaloy
    • Ravi J., Mahmood S.T., Murty K.L. Effects of recrystallization and Nb-additions on texture and mechanical anisotropy of Zircaloy. Nucl. Eng. Design. 148:1994;1-15.
    • (1994) Nucl. Eng. Design , vol.148 , pp. 1-15
    • Ravi, J.1    Mahmood, S.T.2    Murty, K.L.3
  • 28
    • 0018004908 scopus 로고
    • Creep properties of Zr-1 wt.%Nb alloy
    • Thorpe W.R., Smith I.O. Creep properties of Zr-1 wt.%Nb alloy. J. Nucl. Mater. 75:1978;209-219.
    • (1978) J. Nucl. Mater. , vol.75 , pp. 209-219
    • Thorpe, W.R.1    Smith, I.O.2
  • 30
    • 0346243755 scopus 로고    scopus 로고
    • Effect of temperature on mechanical anisotropy of recrystallized Zircaloy-4 Sheet
    • Wang Y., Mathew M.D., Murty K.L. Effect of temperature on mechanical anisotropy of recrystallized Zircaloy-4 Sheet. Metals Mater. 4(4):1998;723-726.
    • (1998) Metals Mater. , vol.4 , Issue.4 , pp. 723-726
    • Wang, Y.1    Mathew, M.D.2    Murty, K.L.3
  • 31
    • 36849138280 scopus 로고
    • Steady state creep of crystals
    • Weertman J. Steady state creep of crystals. J. Appl. Phys. 28:1957;1185-1189.
    • (1957) J. Appl. Phys. , vol.28 , pp. 1185-1189
    • Weertman, J.1
  • 32
    • 0343253714 scopus 로고
    • On the question of void formation in neutron irradiated zirconium
    • Wolfenden A., Farrel K. On the question of void formation in neutron irradiated zirconium. Scripta Met. 6:1972;127-129.
    • (1972) Scripta Met. , vol.6 , pp. 127-129
    • Wolfenden, A.1    Farrel, K.2
  • 33
    • 0342863683 scopus 로고
    • Suppression of void formation in zirconium
    • Zirconium in Nuclear Applications
    • Yoo, M.H., 1994. Suppression of void formation in zirconium. In: Zirconium in Nuclear Applications. ASTM STP 551, pp. 292-307.
    • (1994) ASTM STP , vol.551 , pp. 292-307
    • Yoo, M.H.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.