메뉴 건너뛰기




Volumn 378, Issue 2, 2008, Pages 197-210

Environmentally-assisted cracking behaviour in the transition region of an Alloy182/SA 508 Cl.2 dissimilar metal weld joint in simulated boiling water reactor normal water chemistry environment

Author keywords

[No Author keywords available]

Indexed keywords

ALLOYS; BOILING WATER REACTORS; CHEMISTRY; COMPRESSED AIR; CORROSION; CORROSION FATIGUE; CRACK DETECTION; CRACK PROPAGATION; CRACKING (CHEMICAL); DISSIMILAR METALS; FUSION REACTIONS; HYDROLOGY; IRON; JOINTS (STRUCTURAL COMPONENTS); METALS; MOLECULAR BEAM EPITAXY; NICKEL; NUCLEAR PHYSICS; NUCLEAR REACTORS; PRESSURE; PRESSURE VESSELS; REACTION KINETICS; STEAM POWER PLANTS; STEEL; STRESS CORROSION CRACKING; TWO PHASE FLOW; UNLOADING; WATER COOLED REACTORS; WELDED STEEL STRUCTURES; WELDING;

EID: 48049100556     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2008.06.034     Document Type: Article
Times cited : (95)

References (44)
  • 1
    • 48049124418 scopus 로고    scopus 로고
    • R.M. Horn, P.L. Andresen, J. Hickling, BWR Alloy 182 stress corrosion cracking experience, in: Proceedings of the Fifth International Symposium on Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Fontevraud 5), Cd-ROM, Fontevraud, France, 23-27 September 2002, p. 55.
    • R.M. Horn, P.L. Andresen, J. Hickling, BWR Alloy 182 stress corrosion cracking experience, in: Proceedings of the Fifth International Symposium on Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Fontevraud 5), Cd-ROM, Fontevraud, France, 23-27 September 2002, p. 55.
  • 2
    • 48049100412 scopus 로고    scopus 로고
    • H. Hänninen et al., Dissimilar metal weld joints and their performance in nuclear power plant and oil refinery conditions, VTT Research Notes 2347, VTT, Espoo, Finland, 2006. .
    • H. Hänninen et al., Dissimilar metal weld joints and their performance in nuclear power plant and oil refinery conditions, VTT Research Notes 2347, VTT, Espoo, Finland, 2006. .
  • 3
    • 48049109656 scopus 로고    scopus 로고
    • R.S. Pathania, A.R. McIlree, J. Hickling, Overview of primary water cracking of Alloys 182/82 in PWRs, in: Proceedings of the Fifth International Symposium on Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Fontevraud 5), CD-ROM, Fontevraud, France, 23-27 September 2002, p. 13.
    • R.S. Pathania, A.R. McIlree, J. Hickling, Overview of primary water cracking of Alloys 182/82 in PWRs, in: Proceedings of the Fifth International Symposium on Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Fontevraud 5), CD-ROM, Fontevraud, France, 23-27 September 2002, p. 13.
  • 4
    • 48049125029 scopus 로고    scopus 로고
    • T. Matsunaga, K. Matsunaga, Stress corrosion cracking of CRD stub tube joint and repair at Hamaoka Unit 1, in: Proceedings of Eleventh International Conference on Nuclear Engineering, Paper ICONE11-36056, Shinjuku, Tokyo, Japan, 20-23 April 2003.
    • T. Matsunaga, K. Matsunaga, Stress corrosion cracking of CRD stub tube joint and repair at Hamaoka Unit 1, in: Proceedings of Eleventh International Conference on Nuclear Engineering, Paper ICONE11-36056, Shinjuku, Tokyo, Japan, 20-23 April 2003.
  • 5
    • 48049114254 scopus 로고    scopus 로고
    • A. Yamashita, K. Takeuchi, W. Sagawa, F. Manabe, The stress corrosion cracking at shroud support Tsuruga Unit 1, in: Proceedings of Ninth International Conference on Nuclear Engineering, Paper ICONE 9-66, 8-12 April 2001, Nice, France.
    • A. Yamashita, K. Takeuchi, W. Sagawa, F. Manabe, The stress corrosion cracking at shroud support Tsuruga Unit 1, in: Proceedings of Ninth International Conference on Nuclear Engineering, Paper ICONE 9-66, 8-12 April 2001, Nice, France.
  • 7
    • 48049092281 scopus 로고    scopus 로고
    • H.P. Seifert, S. Ritter, Research and service experience with environmentally-assisted cracking of carbon and low-alloy steels in high-temperature water, SKI-Report 2005:60, Stockholm, Sweden, 2006. .
    • H.P. Seifert, S. Ritter, Research and service experience with environmentally-assisted cracking of carbon and low-alloy steels in high-temperature water, SKI-Report 2005:60, Stockholm, Sweden, 2006. .
  • 8
    • 85039430833 scopus 로고    scopus 로고
    • P.L. Andresen, L.M. Young, P.W. Emigh, R.M. Horn, Stress corrosion crack growth rate behavior of Ni Alloys 182 and 600 in high temperature water, NACE Corrosion 2002, CD-ROM, Paper No. 02510, NACE, 2002.
    • P.L. Andresen, L.M. Young, P.W. Emigh, R.M. Horn, Stress corrosion crack growth rate behavior of Ni Alloys 182 and 600 in high temperature water, NACE Corrosion 2002, CD-ROM, Paper No. 02510, NACE, 2002.
  • 10
  • 11
    • 33745193489 scopus 로고    scopus 로고
    • B. Alexandreanu, O.K. Chopra, W.J. Shack, The effect of grain orientation on the cracking behaviour of Alloy 182 in PWR environment, in: Proceedings of the Twelfth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, Snowbird, Utah, USA, TMS, 14-18 August 2005, p. 579.
    • B. Alexandreanu, O.K. Chopra, W.J. Shack, The effect of grain orientation on the cracking behaviour of Alloy 182 in PWR environment, in: Proceedings of the Twelfth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, Snowbird, Utah, USA, TMS, 14-18 August 2005, p. 579.
  • 12
    • 33745222284 scopus 로고    scopus 로고
    • P. Scott et al., Examination of stress corrosion cracks in Alloy 182 weld metal after exposure to PWR primary water, in: Proceedings of the Twelfth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, TMS, Snowbird, UT, August 14-18 2005, p. 497.
    • P. Scott et al., Examination of stress corrosion cracks in Alloy 182 weld metal after exposure to PWR primary water, in: Proceedings of the Twelfth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, TMS, Snowbird, UT, August 14-18 2005, p. 497.
  • 14
    • 48049091433 scopus 로고    scopus 로고
    • M. Itow et al., Crack growth rates of Alloy 182 in high temperature water, in: Proceedings of the Seventh International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, NACE International, Houston, TX, 1995, p. 541.
    • M. Itow et al., Crack growth rates of Alloy 182 in high temperature water, in: Proceedings of the Seventh International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, NACE International, Houston, TX, 1995, p. 541.
  • 15
    • 48049089658 scopus 로고    scopus 로고
    • M. Itow et al., The effect of corrosion potential on Alloy 182 crack growth rate in high temperature water, in: Proceedings of the Eighth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, La Grange Park, IL, 1997, p. 712.
    • M. Itow et al., The effect of corrosion potential on Alloy 182 crack growth rate in high temperature water, in: Proceedings of the Eighth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, La Grange Park, IL, 1997, p. 712.
  • 16
    • 48049110999 scopus 로고    scopus 로고
    • R. Lindström, P. Lidar, J. Lagerström, Crack growth of Alloy 182 in a simulated primary side PWR environment, in: Proceedings of the Eighth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, La Grange Park, IL, 1997, p. 422.
    • R. Lindström, P. Lidar, J. Lagerström, Crack growth of Alloy 182 in a simulated primary side PWR environment, in: Proceedings of the Eighth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, La Grange Park, IL, 1997, p. 422.
  • 17
    • 0033489217 scopus 로고    scopus 로고
    • W.H. Bamford, J.P. Foster, R.S. Pathania, An investigation of Alloy 182 stress corrosion cracking in simulated PWR environment, in: Proceedings of the Ninth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, TMS, Warrendale, PA, 1999, p. 279.
    • W.H. Bamford, J.P. Foster, R.S. Pathania, An investigation of Alloy 182 stress corrosion cracking in simulated PWR environment, in: Proceedings of the Ninth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, TMS, Warrendale, PA, 1999, p. 279.
  • 18
    • 0033489117 scopus 로고    scopus 로고
    • T. Cassagne et al., Stress corrosion crack growth rate measurements in Alloys 600 and 182 in primary water loops under constant load, in: Proceedings of the Ninth International Conference on Environmental degradation of Materials in Nuclear Power Systems Water Reactors, TMS, Warrendale, PA, 1999, p. 217.
    • T. Cassagne et al., Stress corrosion crack growth rate measurements in Alloys 600 and 182 in primary water loops under constant load, in: Proceedings of the Ninth International Conference on Environmental degradation of Materials in Nuclear Power Systems Water Reactors, TMS, Warrendale, PA, 1999, p. 217.
  • 19
    • 48049103954 scopus 로고    scopus 로고
    • S.L. Hong et al., Measurements of stress corrosion cracking growth rates in weld Alloy 182 in primary water of PWR, in: Proceedings of the Tenth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, Houston, TX, 2001, CD-ROM.
    • S.L. Hong et al., Measurements of stress corrosion cracking growth rates in weld Alloy 182 in primary water of PWR, in: Proceedings of the Tenth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, Houston, TX, 2001, CD-ROM.
  • 20
    • 33745194559 scopus 로고    scopus 로고
    • G.A. White et al., Development of crack growth rate disposition curves for primary water stress corrosion cracking (PWSCC) of Alloy 82, 182 and 132 weldments, in: Proceedings of the Twelfth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, TMS, Snowbird, UT, 2005, p. 511.
    • G.A. White et al., Development of crack growth rate disposition curves for primary water stress corrosion cracking (PWSCC) of Alloy 82, 182 and 132 weldments, in: Proceedings of the Twelfth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, TMS, Snowbird, UT, 2005, p. 511.
  • 21
    • 48049085517 scopus 로고    scopus 로고
    • D.R. Tice et al., Evaluation of test techniques for stress corrosion cracking of dissimilar weldments, in: Proceedings of the Tenth International Conference on Environmental degradation of Materials in Nuclear Power Systems Water Reactors, 2001, Cd-ROM, ANS/TMS/NACE, Lake Tahoe, Nevada, USA, 5-9 August, 2001.
    • D.R. Tice et al., Evaluation of test techniques for stress corrosion cracking of dissimilar weldments, in: Proceedings of the Tenth International Conference on Environmental degradation of Materials in Nuclear Power Systems Water Reactors, 2001, Cd-ROM, ANS/TMS/NACE, Lake Tahoe, Nevada, USA, 5-9 August, 2001.
  • 23
    • 48049089231 scopus 로고    scopus 로고
    • P. Hurst, A.S. Raffel, D.R. Tice, Environmental degradation of dissimilar metal welds, in: Proceedings of the Eighth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, vol. 1, ANS, Amelia Island, FL, USA, 10-14 August 1999, p. 430.
    • P. Hurst, A.S. Raffel, D.R. Tice, Environmental degradation of dissimilar metal welds, in: Proceedings of the Eighth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, vol. 1, ANS, Amelia Island, FL, USA, 10-14 August 1999, p. 430.
  • 26
    • 48049117379 scopus 로고    scopus 로고
    • IC of metallic materials, Annual Book of ASTM Standards, Section 3, vol. 03.01, ISBN 978-0-8031-4310-4, ASTM International, 2007, p. 520.
    • IC of metallic materials, Annual Book of ASTM Standards, Section 3, vol. 03.01, ISBN 978-0-8031-4310-4, ASTM International, 2007, p. 520.
  • 27
    • 48049100192 scopus 로고    scopus 로고
    • K. Reichlin, 2-D FE calibration of DCPD for a bimetallic weld joint, Paul Scherrer Institute, unpublished work.
    • K. Reichlin, 2-D FE calibration of DCPD for a bimetallic weld joint, Paul Scherrer Institute, unpublished work.
  • 29
    • 48049084206 scopus 로고    scopus 로고
    • ASTM E647-05, Standard test method for determining threshold stress intensity factor for environment-assisted cracking of metallic materials, Annual Book of ASTM Standards, Section 3, vol. 03.01, ISBN 978-0-8031-4310-4, ASTM International, 2007, p. 1067.
    • ASTM E647-05, Standard test method for determining threshold stress intensity factor for environment-assisted cracking of metallic materials, Annual Book of ASTM Standards, Section 3, vol. 03.01, ISBN 978-0-8031-4310-4, ASTM International, 2007, p. 1067.
  • 30
    • 48049103736 scopus 로고    scopus 로고
    • ASTM E1681-03, Standard test method for measurement of fatigue crack growth rates, Annual Book of ASTM Standards, Section 3, vol. 03.01, ISBN 978-0-8031-4310-4, ASTM International, 2007, p. 692.
    • ASTM E1681-03, Standard test method for measurement of fatigue crack growth rates, Annual Book of ASTM Standards, Section 3, vol. 03.01, ISBN 978-0-8031-4310-4, ASTM International, 2007, p. 692.
  • 31
    • 48049099055 scopus 로고    scopus 로고
    • Personal communication with C. Jansson (SwedPower AB).
    • Personal communication with C. Jansson (SwedPower AB).
  • 32
    • 0033489344 scopus 로고    scopus 로고
    • F.P. Ford et al., Stress corrosion cracking of low alloy steels under BWR conditions, assessments of crack growth rate algorithms, in: Proceedings of the Ninth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, ANS/NACE/TMS, Newport Beach, CA, 1-5 August 1999, p. 855.
    • F.P. Ford et al., Stress corrosion cracking of low alloy steels under BWR conditions, assessments of crack growth rate algorithms, in: Proceedings of the Ninth International Conference on Environmental degradation of Materials in Nuclear Power Systems - Water Reactors, ANS/NACE/TMS, Newport Beach, CA, 1-5 August 1999, p. 855.
  • 33
    • 48049102185 scopus 로고    scopus 로고
    • The 2004 ASME Boiler and Pressure Vessel Code, Section III, Subsection NB, Appendix I, The American Society of Mechanical Engineers, New York, USA, 2004.
    • The 2004 ASME Boiler and Pressure Vessel Code, Section III, Subsection NB, Appendix I, The American Society of Mechanical Engineers, New York, USA, 2004.
  • 34
    • 48049095261 scopus 로고    scopus 로고
    • O.K. Chopra, W.J. Shack, Effect of LWR coolant environment on the fatigue life of reactor materials, Final report, NUREG/CR-6909, ANL-06/08, US NRC, Washington, DC, USA, February 2007. .
    • O.K. Chopra, W.J. Shack, Effect of LWR coolant environment on the fatigue life of reactor materials, Final report, NUREG/CR-6909, ANL-06/08, US NRC, Washington, DC, USA, February 2007. .
  • 37
    • 47049117552 scopus 로고    scopus 로고
    • H.P. Seifert, S. Ritter, Corros. Sci, 2008, doi:10.1016/j.corsci.2008.03.010.
    • H.P. Seifert, S. Ritter, Corros. Sci, 2008, doi:10.1016/j.corsci.2008.03.010.
  • 39
    • 48049097567 scopus 로고    scopus 로고
    • O.K. Chopra, W.K. Soppet, W.J. Shack, Effects of cold work, and water chemistry on corrosion fatigue and stress corrosion cracking of nickel alloys and welds, NUREG/CR-6721, ANL/01/07, US NRC, Washington, DC, USA, April 2001.
    • O.K. Chopra, W.K. Soppet, W.J. Shack, Effects of cold work, and water chemistry on corrosion fatigue and stress corrosion cracking of nickel alloys and welds, NUREG/CR-6721, ANL/01/07, US NRC, Washington, DC, USA, April 2001.
  • 41
    • 48049122905 scopus 로고    scopus 로고
    • F.P. Ford, P.L. Andresen, Corrosion fatigue of A533B/A508 pressure vessel steels in 288 °C water, in: Third International IAEA Specialist's Meeting on Subcritical Crack Growth, vol. 1, W. Cullen (Ed.), NUREG/CP-0112, Moscow, USSR, 14-17 May 1990, p. 105.
    • F.P. Ford, P.L. Andresen, Corrosion fatigue of A533B/A508 pressure vessel steels in 288 °C water, in: Third International IAEA Specialist's Meeting on Subcritical Crack Growth, vol. 1, W. Cullen (Ed.), NUREG/CP-0112, Moscow, USSR, 14-17 May 1990, p. 105.
  • 42
    • 48049124170 scopus 로고    scopus 로고
    • F.P. Ford, P.L. Andresen, Stress corrosion cracking of low-alloy steels in 288 °C water, NACE Corrosion 1989, NACE, New Orleans, Houston, USA, Paper No. 498, p. 498-1.
    • F.P. Ford, P.L. Andresen, Stress corrosion cracking of low-alloy steels in 288 °C water, NACE Corrosion 1989, NACE, New Orleans, Houston, USA, Paper No. 498, p. 498-1.
  • 44
    • 48049090990 scopus 로고    scopus 로고
    • C. Amzallag et al., Stress corrosion life experience of 182 and 82 welds in French PWRs, in: Proceedings of the Fifth International Symposium on Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Fontevraud 5), Cd-ROM, Fontevraud, France, 23-27 September 2002, p. 69.
    • C. Amzallag et al., Stress corrosion life experience of 182 and 82 welds in French PWRs, in: Proceedings of the Fifth International Symposium on Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Fontevraud 5), Cd-ROM, Fontevraud, France, 23-27 September 2002, p. 69.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.