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NTIS 바로가기Journal of welding and joining = 대한용접·접합학회지, v.33 no.1, 2015년, pp.14 - 23
유호천 (한국과학기술정보연구원 ReSEAT 프로그램)
Recent developing tendency of nuclear power plant are studied by searching of NDSL, KIPRIS, Science Direct and so on. Welding materials such as low alloyed steels, stainless steels, nickel-based alloys, zirconium alloy and welding methods such as narrow gap welding, laser beam welding, friction stir...
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핵심어 | 질문 | 논문에서 추출한 답변 |
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원자로압력용기의 내부표면에 세심한 관리가 필요한 이유는? | 원자력발전 설비 내의 원자로압력용기(RPV)는 두께가 200mm에 달하는 저합금강으로 만들어지는데, 원자로압력용기의 내부표면은 원자로냉각제에 의한 환경부식에 민감하여 몇 mm두께의 오스테나이트계 스테인리스강을 오버레이 클래딩으로 보호되고 있지만 이 부분에서의 가압열충격은 가압경수로(PWR)의 파괴를 일으키는 주요 원인으로 작용할 수 있기 때문에 세심한 관리가 필요하다1),2). | |
오버레이용접에 사용되는 Alloy 690의 장단점은? | Alloy 600은 일차수 응력부식균열(PWSCC : Primary Water Stress Corrosion Cracking)에 민감한 재료로 알려져 있다16). 이에 대비하여 Alloy 690은 크롬함유량을 증가시켜 반연속적인 입계탄화물에 의해 응력부식균열의 저항성을 향상시킨 소재이다. 그러나 Alloy 690 용접금속은 고온균열에 민감하고 기공, 용입불량 등의 결함이 발생하기 쉽다. 특히 연성저하 응고구간에서 발생하는 연성저하균열 결함에 민감하여 이를 방지하기 위해서는 적절한 시공조건 설정과 용접재료의 선택이 중요하다15). | |
AISI 316L 사용시 주의사항은? | AISI 316L은 높은 응력부식균열 저항성으로 인하여 원자력발전 설비에 자주 사용되고 있지만 용접 가공열처리 사이클로 인하여 기계적 성질과 재료의 조건, 예를 들면 용접 접합부 근처에 소성변형과 냉간가공에 따라 응력부식균열에 의한 열화에 심각한 영향을 미치므로 유의해야 한다10). 페라이트와 오스테나이트 2상으로 구성된 듀플렉스 스테인리스강(Z3CN 20. |
Kameyama Masashi, Nuclear Power supply(Japan Nuclear Safety Institute), Journal of the Japan Welding Society, 82 (1) (2013), 57-63 (in Japanese)
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C. Brillaud et al., Effects of radiation on materials: 20th International Symposium, ASTM STP 1405, American Society for Testing and Materials, West Conshohocken, (2001)
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A. Ulbricht et al., Small-angle neutron scattering investigation of as-irradiated, annealed and reirradiated reactor pressure vessel weld material of decommissioned react, Journal of Nuclear Materials, 416 (2011), 111-116
B. Gurovich et al., Evolution of weld metals nanostructure and properties under irradiation and recovery annealing of VVER-type reactors, Journal of Nuclear Materials, 434 (2013), 72-84
Kameyama Masashi, Nuclear power(Design), Journal of the Japan Welding Society, 83 (4) (2014), 270-274 (in Japanese)
K. Suzuki et al., Application of high strength MnMoNi steel to pressure vessels for nuclear power plant, Nuclear Engineering and Design, 206 (2001), 261-278
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Ahmed Elmesalamy et al., A comparison of residual stresses in multi pass narrow gap laser welds and gas-tungsten arc welds in AISI 316L stainless steel, International Journal of Pressure Vessels and Piping, 113 (2014), 49-59
Y. Q. Wang et al., Localized Corrosion of Thermally Aged Cast Duplex Stainless Steel for Primary Coolant Pipes of Nuclear Power Plant, Procedia Engineering, 36 (2012), 88-95
T. Yonezawa, 2.08 Nickel Alloys, Properties and Characteris- tics, Tohoku University, Japan Elsevier Ltd. (2012), 233-266
A. J. Ramirez et al., High temperature behavior of Ni-base weld metal Part II-insight into the mechanism for ductility dip cracking, Mater. Sci. Eng. A 380 (2004), 245-258
A. J. Ramirez et al., Improving the ductility-dip cracking resistance of Ni-base alloys, J. Mater. Process. Technol. 179 (2006), 212-218
In Chul Jung et al., Overlay Welding of Inconel Material for Nuclear Power Components, Journal of KWJS, 27 (2) (2009), 122-124
Sung-Sik Kang et al., The experience and analysis of vent pipe PWSCC in PWR vessel head penetration, Nuclear Engineering and Design, 269 (2014), 291-298
http://www.meti.go.jp/committe/materials2/, Ministry of Economy, Trade and Industry homepage, download-files/g100121a05j.pdf
Hwa Teng Lee et al., Numerical and experimental investigation into effect of temperature field on sensitization of Alloy 690 butt welds fabricated by gas tungsten arc welding and laser beam welding, Journal of Materials Processing Technology, 210 (2010), 1636-1645
Seong Sik Hwang et al., Review of PWSCC and mitigation management strategies of Alloy 600 materials of PWRs, Journal of Nuclear Materials, 443 (2013), 321-330
S. M. Bruemmer et al., Characterization of defects in alloy 52, 152 and 52M welds, in: Proc. 14th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems, ANS, LaGrange Park, IL, (2009), 319-332.
A. J. Ramirez et al., Improving the ductility-dip cracking resistance of Ni-base alloys, J. Mater. Process. Technol. 179 (2006), 212-218
L. Li, R. W. Messler Jr., Metall. Mater. Trans. A-Phys. Metall. Mater. Sci. 33A (2002) 2031-2042
Qunjia Peng et al., Effect of chemical composition on grain boundary microchemistry and stress corrosion cracking in Alloy 182, Corrosion Science, 67 (2013) 91-99
M. K. Samal et al., Investigation of failure behavior of two different types of Zircaloy clad tubes used as nuclear reactor fuel pins, Engineering Failure Analysis, 18 (2011), 2042-2053
N. Boutarek et al., Microstructure change in the interface of CO2 laser welded zirconium alloys, Physics Procedia, 2 (2009), 1159-1165
Yong-Ding Lin et al., Effects of beam offset on mechanical properties and corrosion resistance of Alloy 690-SUS 304L EBW joints for nuclear power plant, Journal of Nuclear Materials, 401 (2010), 78-85
Wanjae Kim et al., Parametric study for Welding Residual Stresses in Nozzle of Nuclear Power Plants using Finite Element Method, Autumn Annual Meeting of The Korean Society of Mechanical Engineers, (2008), 104-109 (in Korean)
Q. Peng et al., SCC behavior in the transition region of an Alloy 182, SA508 Cl.2 dissimilar weld joint under simulated BWR-NWC conditions, Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System, Water Reactors, (2005), 589-599
T. R. Allen et al., Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System, Water Reactors, (2005), 833-842
G. S. Was et al., Proceedings of the 11th International Conference on Environmental Degradation of Materials in Nuclear Power System, Water Reactors, (2003), 1071-1081
J. Y. Huang et al., Effects of heat treatment and chromium content on the environmentally assisted cracking behavior of the dissimilar metal welds in simulated BWR coolant environments, Corrosion Science, 75 (2013), 386-399
D. J. Paraventi et al., Assessment of the interaction of variables in the intergranular stress corrosion crack growth rate behavior of alloys 600, 82, and 182, The 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, (2007), 19-23
J. Y. Huang et al., Effects of heat treatment and chromium content on the environmentally assisted cracking behavior of the dissimilar metal welds in simulated BWR coolant environments, Corrosion Science, 75 (2013), 386-399
Lee, Byoung-Hoon et al., Welding Technology and Application in Nuclear Power Plant,, Machinery and Materials, 19-1 (2007), 30-39 (in Korean)
Nikulina A. V, Zirconium alloys in nuclear power engineering, Met Sci Heat Treat, 46 (11-12), (2004) 458-462
Seung Wan Woo et al., The Application of Narrow-Gap Welding Process for SA 106 Gr.C in Nuclear Power Plant, Autumn Annual Meeting of The Korean Society of Mechanical Engineers, (2014), 96-101 (in Korean)
A. Traidia et al., On the effects of gravity and sulfur content on the weld shape in horizontal narrow gap GTAW of stainless steels, Journal of Materials Processing Technology, 213 (2013), 1128-1138
Long Tan et al., Effect of geometric construction on residual stress distribution indesigning a nuclear rotor joined by multipass narrow gap welding, Fusion Engineering and Design, 89 (2014), 456-465
C. Liu et al., Numerical investigation on residual stress distribution and evolution during multipass narrow gap welding of thick-walled stainless steel pipes, Fusion Engineering and Design, 86-4 (2011), 288-295
P. D. Gupta et al., Laser Applications in Indian Nuclear Power Programme, Energy Procedia,7 (2011), 560-576
Gilner, A. et al., Laser applications in microtechnology, JMPT, 167 (2005), 494-498
Kim, D. J et al., Repair welding of etched tubular components of nuclear power plant by Nd:YAG laser, JMPT, 14 (2001), 51-56
Zhang X et al., Welding of thick stainless steel plates up to 50mm with high brightness lasers, Journal of Laser Appl. 23:022002, (2011)
Y. C. Chen et al., Banded structure and its distribution in friction stir processing of 316L austenitic stainless steel, Journal of Nuclear Materials, 420 (2012), 497-500
Lars Cederqvist et al., Reliability study of friction stir welded copper canisters containing Sweden's nuclear waste, Reliability Engineering and System Safety, 93 (2008), 1491-1499
Tanigawa et al., Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules, Fusion Engineering and Design, 83 (2008), 1471-1476
E. Rajendra Kumar et al., Preliminary design of Test Blanket Module for ITER, Fusion Engineering and Design, 83 (2008), 1169-1172
Baldev Raj et al, Development of Reduced Activation Ferritic-Martensitic Steels and fabrication technologies for Indian test blanket module, Journal of Nuclear Materials, 417 (2011), 72-76
Y. Poitevin et al., Development of welding technologies for the manufacturing of European Tritium Breeder blanket modules, Journal of Nuclear Materials, 417 (2011), 36-42
MPR Associates, INC. Internal mechanical stress improvement method for mitigating stress corrosion cracking in weld areas of nuclear power plant piping, WO2014/012116, (2014)
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