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Volumn 232, Issue 1, 2004, Pages 85-96

Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations PART II. Best-fitted parabolic correlations

Author keywords

[No Author keywords available]

Indexed keywords

CORRELATION METHODS; HYDROGEN; ISOTHERMS; MATHEMATICAL MODELS; NUCLEAR REACTOR ACCIDENTS; OXIDATION; REACTION KINETICS; RISK ASSESSMENT;

EID: 3242660013     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2004.02.014     Document Type: Article
Times cited : (50)

References (14)
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    • July 2001
    • Fichot, F., et al., 2001. ICARE/CATHARE: A Computer Code for Analysis Of Severe Accidents in LWRs, ICARE2 V3mod1: Description of Physical Models. Technical note DRS/SEMAR 00/03, July 2001.
    • (2001) Technical Note , vol.DRS-SEMAR 00-03
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    • Experimental and theoretical results of cladding oxidation under severe fuel-damage conditions
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    • Hofmann, P., Neitzel, H.J., 1987. Experimental and theoretical results of cladding oxidation under severe fuel-damage conditions. In: Adamson, R.B., Van Swan, L.F.P. (Eds.), Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939. American Society for Testing and Materials, Philadelphia, pp. 504-538.
    • (1987) Zirconium in the Nuclear Industry: Seventh International Symposium , pp. 504-538
    • Hofmann, P.1    Neitzel, H.J.2
  • 6
    • 0021375801 scopus 로고
    • Verification of the from model for zircaloy oxidation during temperature transients
    • Iglesias F.C., et al. Verification of the from model for zircaloy oxidation during temperature transients. J. Nucl. Mater. 130:1985;36-44.
    • (1985) J. Nucl. Mater. , vol.130 , pp. 36-44
    • Iglesias, F.C.1
  • 7
    • 0022767405 scopus 로고
    • Oxidation kinetics and related phenomena of Zircaloy-4 fuel cladding exposed to high temperature steam and hydrogen-steam mixtures under PWR accident conditions
    • Leistikow S., Schanz G. Oxidation kinetics and related phenomena of Zircaloy-4 fuel cladding exposed to high temperature steam and hydrogen-steam mixtures under PWR accident conditions. Nucl. Eng. Des. 103:1987;65-84.
    • (1987) Nucl. Eng. Des. , vol.103 , pp. 65-84
    • Leistikow, S.1    Schanz, G.2
  • 8
    • 0028465906 scopus 로고
    • Materials chemistry and transport modeling for severe accident analyses in light-water reactors, I: External cladding oxidation
    • Olander D.R. Materials chemistry and transport modeling for severe accident analyses in light-water reactors, I: External cladding oxidation. Nucl. Eng. Des. 148:1994;253-271.
    • (1994) Nucl. Eng. Des. , vol.148 , pp. 253-271
    • Olander, D.R.1
  • 9
    • 0018490980 scopus 로고
    • Oxygen diffusion in the oxide and alpha phases during reaction of Zircaloy-4 with steam from 1000 °C to 1500 °C
    • Pawel R.E. Oxygen diffusion in the oxide and alpha phases during reaction of Zircaloy-4 with steam from 1000. °C to 1500 °C J. Electrochem. Soc. 126(7):1979;1111-1118.
    • (1979) J. Electrochem. Soc. , vol.126 , Issue.7 , pp. 1111-1118
    • Pawel, R.E.1
  • 10
    • 84916145771 scopus 로고
    • Oxidation of zircaloy-4 in steam at 1300 °C to 2400 °C
    • Adamson, R.B., Van Swan, L.F.P. (Eds.), ASTM STP 939. American Society for Testing and Materials, Philadelphia
    • Prater, J.T., Courtright, E.L., 1987. Oxidation of Zircaloy-4 in Steam at 1300 °C to 2400 °C. In: Adamson, R.B., Van Swan, L.F.P. (Eds.), Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939. American Society for Testing and Materials, Philadelphia, pp. 489-503.
    • (1987) Zirconium in the Nuclear Industry: Seventh International Symposium , pp. 489-503
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    • Cambridge University Press (Chapter 10)
    • Press, W.H., et al., 1986. Numerical Recipes. Cambridge University Press (Chapter 10).
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    • Press, W.H.1
  • 12
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    • Advanced treatment of Zircaloy cladding high-temperature oxidation in severe accident code calculations, Part I. Experimental database and basic modeling
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* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.