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Volumn 240, Issue 5, 2010, Pages 985-994

Effect of dissolved oxygen on oxidation and hydrogen pick up behaviour-Zircaloy vs Zr-Nb alloys

Author keywords

[No Author keywords available]

Indexed keywords

DISSOLVED OXYGEN CONTENTS; DISSOLVED OXYGEN LEVELS; ELECTROCHEMICAL IMPEDANCE; FREE OXYGEN; GOOD CORRELATIONS; HYDROGEN PICK UP; IN-SITU; LEVEL CHANGE; LONG TERM EXPOSURE; NUCLEAR POWER REACTORS; OXIDATION BEHAVIOURS; PREFERENTIAL REACTION; RE-CIRCULATION LOOPS; SHORT-TERM EXPOSURE; WEIGHT GAIN; ZIRCALOY; ZIRCALOY-2; ZR-NB ALLOYS;

EID: 77949269588     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2009.12.021     Document Type: Article
Times cited : (48)

References (36)
  • 4
    • 77949268136 scopus 로고    scopus 로고
    • B 353, 2007. Standard specification for wrought zirconium and zirconium alloy seamlessand welded tubes for nuclear service, ASTM Annual Book of Standards.
    • B 353, 2007. Standard specification for wrought zirconium and zirconium alloy seamlessand welded tubes for nuclear service, ASTM Annual Book of Standards.
  • 5
    • 77949274306 scopus 로고    scopus 로고
    • B 811, 2007. Standard specification for wrought zirconium and zirconium alloy seamlessand welded tubes for nuclear service, ASTM Annual Book of Standards.
    • B 811, 2007. Standard specification for wrought zirconium and zirconium alloy seamlessand welded tubes for nuclear service, ASTM Annual Book of Standards.
  • 7
    • 47749122911 scopus 로고    scopus 로고
    • Kinetic parameters of the oxidation of zirconium alloys in simulated WWER water-effect of KOH content
    • Bojinov M., Kinnunen Cai.W., and Saario P.T. Kinetic parameters of the oxidation of zirconium alloys in simulated WWER water-effect of KOH content. J. Nucl. Mater. 378 (2008) 45-54
    • (2008) J. Nucl. Mater. , vol.378 , pp. 45-54
    • Bojinov, M.1    Kinnunen, Cai.W.2    Saario, P.T.3
  • 10
    • 0001012609 scopus 로고    scopus 로고
    • Conduction mechanism of the passive film on iron based on contact electric impedance and resistance measurements
    • Bojinov M., Laitinen T., Mäkelä K., and Saario T. Conduction mechanism of the passive film on iron based on contact electric impedance and resistance measurements. J. Electrochem. Soc. 148 (2001) B243-B250
    • (2001) J. Electrochem. Soc. , vol.148
    • Bojinov, M.1    Laitinen, T.2    Mäkelä, K.3    Saario, T.4
  • 12
    • 0014863676 scopus 로고
    • The influence of oxide stress on the breakaway oxidation of zircaloy-2
    • Bradhurst D.H., and Heuer P.M. The influence of oxide stress on the breakaway oxidation of zircaloy-2. J. Nucl. Mater. 37 (1970) 35
    • (1970) J. Nucl. Mater. , vol.37 , pp. 35
    • Bradhurst, D.H.1    Heuer, P.M.2
  • 13
    • 0342585912 scopus 로고
    • Effects of irradiation on the oxidation of zirconium alloys in high temperature aqueous environments: a review
    • Cox B. Effects of irradiation on the oxidation of zirconium alloys in high temperature aqueous environments: a review. J. Nucl. Mater. 28 (1968) 1
    • (1968) J. Nucl. Mater. , vol.28 , pp. 1
    • Cox, B.1
  • 14
    • 0344363106 scopus 로고
    • Comments on the paper, the influence of oxide stress on the breakaway oxidation of Zircaloy-2
    • Cox B. Comments on the paper, the influence of oxide stress on the breakaway oxidation of Zircaloy-2. J. Nucl. Mater. 41 (1971) 96-100
    • (1971) J. Nucl. Mater. , vol.41 , pp. 96-100
    • Cox, B.1
  • 15
    • 77949268838 scopus 로고
    • Long term corrosion and hydriding of Zircaloy-4 fuel clad in commercial pressurised water reactors with forced convective heat transfer
    • Washington DC, 2-7 May
    • Dalgaard S.B. Long term corrosion and hydriding of Zircaloy-4 fuel clad in commercial pressurised water reactors with forced convective heat transfer. Extended Abstracts of the Proceedings of the Electrochemical Society. Washington DC, 2-7 May (1976)
    • (1976) Extended Abstracts of the Proceedings of the Electrochemical Society
    • Dalgaard, S.B.1
  • 16
    • 0004708774 scopus 로고
    • Corrosion of Zircaloy fuel cladding-the influence of high heat fluxes
    • Dyce I.H. Corrosion of Zircaloy fuel cladding-the influence of high heat fluxes. Nucl. Eng. 9 (1964) 253-255
    • (1964) Nucl. Eng. , vol.9 , pp. 253-255
    • Dyce, I.H.1
  • 17
    • 77949268837 scopus 로고    scopus 로고
    • E 1447, 2005. Standard test method for determination of hydrogen in titanium and titanium alloys by the inert gas fusion thermal conductivity/infrared detection method, ASTM Annual Book of Standards.
    • E 1447, 2005. Standard test method for determination of hydrogen in titanium and titanium alloys by the inert gas fusion thermal conductivity/infrared detection method, ASTM Annual Book of Standards.
  • 18
    • 77949268135 scopus 로고    scopus 로고
    • G 2 M, 2005. Standard test method for corrosion testing of products of zirconium, hafnium and their alloys in water at 633 K or in steam at 673 K, ASTM Annual Book of Standards.
    • G 2 M, 2005. Standard test method for corrosion testing of products of zirconium, hafnium and their alloys in water at 633 K or in steam at 673 K, ASTM Annual Book of Standards.
  • 19
    • 54949156586 scopus 로고    scopus 로고
    • Advances in zirconium technology for nuclear reactor application
    • De P.K. (Ed). September 11-13, 2002 at Bhabha Atomic Research Centre, Mumbai
    • Ganguly C. Advances in zirconium technology for nuclear reactor application. In: De P.K. (Ed). Proceedings of the symposium zirconium. September 11-13, 2002 at Bhabha Atomic Research Centre, Mumbai (2002) 1
    • (2002) Proceedings of the symposium zirconium , pp. 1
    • Ganguly, C.1
  • 20
    • 85069589238 scopus 로고
    • Corrosion of Zirconium Base Alloys-An Overview
    • Lowe@@Jr. A.L., and Parry G.W. (Eds), American Society for Testing and Materials pp. 211-235
    • Hillner E. Corrosion of Zirconium Base Alloys-An Overview. In: Lowe@@Jr. A.L., and Parry G.W. (Eds). Zirconium in the Nuclear Industry, ASTM STP 633 (1977), American Society for Testing and Materials pp. 211-235
    • (1977) Zirconium in the Nuclear Industry, ASTM STP 633
    • Hillner, E.1
  • 21
    • 77949274303 scopus 로고    scopus 로고
    • IAEA TECDOC-996-996, 1998. Waterside corrosion of zirconium alloys in nuclear power plants, International Atomic Energy Agency Technical Document 996, IAEA, Vienna, Austria.
    • IAEA TECDOC-996-996, 1998. Waterside corrosion of zirconium alloys in nuclear power plants, International Atomic Energy Agency Technical Document 996, IAEA, Vienna, Austria.
  • 25
    • 0026698498 scopus 로고
    • Electrochemical potential measurement under simulated BWR water chemistry conditions
    • Lin C.C., Smith F.R., Ichikawa N., and Itow M. Electrochemical potential measurement under simulated BWR water chemistry conditions. Corrosion 48 (1992) 16-28
    • (1992) Corrosion , vol.48 , pp. 16-28
    • Lin, C.C.1    Smith, F.R.2    Ichikawa, N.3    Itow, M.4
  • 27
    • 0035336756 scopus 로고    scopus 로고
    • Oxidation of Zircaloy-2 and Zircaloy-4 in water and lithiated water at 360 °C
    • Oscarsson M., Ahlberg E., and Pettersson K. Oxidation of Zircaloy-2 and Zircaloy-4 in water and lithiated water at 360 °C. J. Nucl Mater. 295 (2001) 97-108
    • (2001) J. Nucl Mater. , vol.295 , pp. 97-108
    • Oscarsson, M.1    Ahlberg, E.2    Pettersson, K.3
  • 28
    • 0032308928 scopus 로고    scopus 로고
    • Contact electric resistance (CER) technique for in-situ characterization of surface films
    • Forum 289-292
    • Saario T., Laitinen T., and Piippo J. Contact electric resistance (CER) technique for in-situ characterization of surface films. Mater. Sci. (1998) 193 Forum 289-292
    • (1998) Mater. Sci. , pp. 193
    • Saario, T.1    Laitinen, T.2    Piippo, J.3
  • 29
    • 0024057289 scopus 로고    scopus 로고
    • Modeling of coolant radiolysis in the primary heat transport system of Candu reactors-effect of coolant boiling
    • Sava R.L. Modeling of coolant radiolysis in the primary heat transport system of Candu reactors-effect of coolant boiling. J. Nucl. Mater. 158 (1998) 240-252
    • (1998) J. Nucl. Mater. , vol.158 , pp. 240-252
    • Sava, R.L.1
  • 32
    • 33646485292 scopus 로고    scopus 로고
    • Design and development of the AHWR-the Indian thorium fuelled innovative nuclear reactor
    • Sinha R.K., and Kakodkar A. Design and development of the AHWR-the Indian thorium fuelled innovative nuclear reactor. Nucl. Eng. Des. 236 (2006) 683-700
    • (2006) Nucl. Eng. Des. , vol.236 , pp. 683-700
    • Sinha, R.K.1    Kakodkar, A.2
  • 33
    • 0029392149 scopus 로고
    • Evolution of microstructure during fabrication of Zr-2.5 wt pct Nb alloy pressure tubes
    • Srivastava D., Dey G.K., and Banerjee S. Evolution of microstructure during fabrication of Zr-2.5 wt pct Nb alloy pressure tubes. Metall. Mater. Trans. 26A (1995) 2707
    • (1995) Metall. Mater. Trans. , vol.26 A , pp. 2707
    • Srivastava, D.1    Dey, G.K.2    Banerjee, S.3
  • 34
    • 34447521053 scopus 로고
    • Application related metallurgy of zirconium, niobium and beryllium
    • Sundaram C.V. Application related metallurgy of zirconium, niobium and beryllium. Trans. Indian Inst. Metals 39 (1986) 12
    • (1986) Trans. Indian Inst. Metals , vol.39 , pp. 12
    • Sundaram, C.V.1
  • 35
    • 77949268132 scopus 로고
    • Calculation of the safe Life time expectancy of zirconium alloy canning in the fuel elements of the NERO reactor
    • 41, Reactor Centrum, Nederland, Petten
    • Van der Linde, A., 1965. Calculation of the safe Life time expectancy of zirconium alloy canning in the fuel elements of the NERO reactor, RCN Report 41, Reactor Centrum, Nederland, Petten.
    • (1965) RCN Report
    • Van der Linde, A.1
  • 36
    • 76649143086 scopus 로고    scopus 로고
    • Effect of water chemistry and composition on microstructural evolution of oxide on Zr alloys
    • Zhou B.X., Li Q., Yao M.Y., Liu W.Q., and Chu Y.L. Effect of water chemistry and composition on microstructural evolution of oxide on Zr alloys. J. ASTM Int. 5 2. (2008)
    • (2008) J. ASTM Int. , vol.5 , Issue.2
    • Zhou, B.X.1    Li, Q.2    Yao, M.Y.3    Liu, W.Q.4    Chu, Y.L.5


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.