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Статті в журналах з теми "Irradiation assisted stress corrosion cracking"
McNeil, M. B. "Irradiation assisted stress corrosion cracking." Nuclear Engineering and Design 181, no. 1-3 (May 1998): 55–60. http://dx.doi.org/10.1016/s0029-5493(97)00334-8.
Повний текст джерелаKenik, E. A., R. H. Jones, and G. E. C. Bell. "Irradiation-assisted stress corrosion cracking." Journal of Nuclear Materials 212-215 (September 1994): 52–59. http://dx.doi.org/10.1016/0022-3115(94)90033-7.
Повний текст джерелаTsukada, Takashi. "Irradiation Assisted Stress Corrosion Cracking (IASCC)." Zairyo-to-Kankyo 52, no. 2 (2003): 66–72. http://dx.doi.org/10.3323/jcorr1991.52.66.
Повний текст джерелаKain, V., S. B. Chafle, D. Feron, B. Tanguy, C. Colin, and C. Gonnier. "ICONE23-2044 IRRADIATION ASSISTED STRESS CORROSION CRACKING AND THE JULES HOROWITZ MATERIAL TEST REACTOR." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23 (2015): _ICONE23–2—_ICONE23–2. http://dx.doi.org/10.1299/jsmeicone.2015.23._icone23-2_18.
Повний текст джерелаCui, Bai, Michael D. McMurtrey, Gary S. Was, and Ian M. Robertson. "Micromechanistic origin of irradiation-assisted stress corrosion cracking." Philosophical Magazine 94, no. 36 (November 21, 2014): 4197–218. http://dx.doi.org/10.1080/14786435.2014.982744.
Повний текст джерелаScott, P. "A review of irradiation assisted stress corrosion cracking." Journal of Nuclear Materials 211, no. 2 (August 1994): 101–22. http://dx.doi.org/10.1016/0022-3115(94)90360-3.
Повний текст джерелаWas, Gary S., and Peter L. Andresen. "Irradiation-assisted stress-corrosion cracking in austenitic alloys." JOM 44, no. 4 (April 1992): 8–13. http://dx.doi.org/10.1007/bf03222812.
Повний текст джерелаHojná, Anna. "Irradiation-Assisted Stress Corrosion Cracking and Impact on Life Extension." CORROSION 69, no. 10 (October 2013): 964–74. http://dx.doi.org/10.5006/0803.
Повний текст джерелаRossi, F., F. Fumagalli, A. Ruiz-Moreno, P. Moilanen, and P. Hähner. "Membrane bulge test rig for irradiation-assisted stress-corrosion cracking." Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 479 (September 2020): 80–92. http://dx.doi.org/10.1016/j.nimb.2020.06.012.
Повний текст джерелаSmith, Stuart A., Brock Gause, David Plumley, and Masao J. Drexel. "Irradiation-Assisted Stress-Corrosion Cracking of Nitinol During eBeam Sterilization." Journal of Materials Engineering and Performance 21, no. 12 (October 17, 2012): 2638–42. http://dx.doi.org/10.1007/s11665-012-0396-8.
Повний текст джерелаДисертації з теми "Irradiation assisted stress corrosion cracking"
Duff, Jonathon Andrew. "The influence of grain boundary structure in proton irradiated stainless steel on susceptibility to irradiation assisted stress corrosion cracking." Thesis, University of Manchester, 2008. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.496690.
Повний текст джерелаHilton, Bruce A. "Irradiation assisted stress corrosion cracking susceptibility of low fluence stainless steels evaluated by in-flux slow strain rate tests." Thesis, Massachusetts Institute of Technology, 1996. http://hdl.handle.net/1721.1/42810.
Повний текст джерелаLe, Millier Morgane. "Fragilisation des aciers inoxydables austénitiques sous irradiation : évolution de la microstructure et amorçage de la corrosion sous contrainte assistée par l'irradiation en milieu REP." Thesis, Paris, ENMP, 2014. http://www.theses.fr/2014ENMP0047/document.
Повний текст джерелаThis work deals with the microstructure evolution of austenitic stainless steels under irradiation and the consequences of this evolution on their behavior in PWR environment. 304L steel was proton-irradiated at 360°C to 5 and 10 dpa. Following these irradiations, IASCC was studied in a 350°C simulated primary water, with strain fields measurements using digital image correlation. In parallel, thin foils were irradiated in situ with Ni++ ions at 500°C up to 2 dpa with simultaneous helium implantation. These experiments allowed us (i) to have a better understanding of the key parameters responsible of the IASCC initiation in reducing environment thanks to the coupling between microstructure, mechanical fields and cracking (ii) to define the role of helium on the nucleation and evolution of radiation defects. It turns out that, in the studied conditions, the implantation of helium has only a limited effect on the dislocation loop and cavity populations for ratios lower than 800 appm He/dpa. Cavities were observed with and without helium, including in the grain boundaries which could be a factor of embrittlement. The stress corrosion cracking tests resulted in an increase of the crack density with the increase of the macroscopic deformation and in a bigger opening and on-surface propagation of cracks after a sequential loading. These cracks propagate deeply in the irradiated layer partly because of the overstress generated by the strong gradient of mechanical properties between the irradiated and non-irradiated zones of the material. The activated deformation mechanisms are complex and twinning was observed after 2 and 10% of macroscopic deformation. The deformation after irradiation is strongly localized in transgranular bands and around some grain boundaries, but it appears that the strong deformation around boundaries is not an initiation criterion. Deformation discontinuity on both sides of cracked boundaries is systematically observed and evaluation of the local stress state appears to be essential to describe IASCC initiation. This local stress state could be calculated by finite elements, taking into account the experimental results in terms of crystallographic orientation fields or Kinematics fields strong heterogeneity of local deformation quantified in this work
Riad, Soukaina. "Vers une modélisation de la corrosion sous contrainte assistée par l'irradiation du superalliage 718." Electronic Thesis or Diss., Ecole centrale de Nantes, 2022. http://www.theses.fr/2022ECDN0039.
Повний текст джерелаInconel 718 alloy is renowned for having excellent corrosion resistance, very high mechanical strength and good resistance to irradiation. Thus, it is a material of choice within a nuclear power reactor for parts subjected to extreme stresses (springs, retaining systems,...). However, failures in service have been observed in this material under irradiationassisted stress corrosion cracking phenomenon. This thesis aims to bring new elements of understanding of this complex phenomenon from the point of view of numerical modeling. The stress corrosion cracking process is modeled by the phase field fracture method. A unified implementation, able to deal with inter and intergranular fracture, is proposedand allows to couple efficiently different scales of work (from continuous medium to polycrystal) and different physics (mechanics of continuous and generalized media and internal oxidation). This modeling allows to propose simulations of the complex stages of stress corrosion cracking, namely initiation, coalescence and propagation
Ghasemi, Rohollah. "Hydrogen-assisted stress corrosion cracking of high strength steel." Thesis, KTH, Skolan för kemivetenskap (CHE), 2011. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-50416.
Повний текст джерелаFegan, J. J. H. "Environment assisted cracking of deaerator steels in high temperature water." Thesis, University of Newcastle Upon Tyne, 1995. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.260856.
Повний текст джерелаYang, Dong. "Factors affecting stress assisted corrosion cracking of carbon steel under industrial boiler conditions." Diss., Atlanta, Ga. : Georgia Institute of Technology, 2008. http://hdl.handle.net/1853/24809.
Повний текст джерелаCommittee Co-Chair: Preet M. Singh; Committee Co-Chair: Richard W. Neu; Committee Member: Hamid Garmestani; Committee Member: Timothy Patterson; Committee Member: W. Steven Johnson.
Cano-Castillo, U. "Environment-assisted cracking of spray-formed Al-alloy and Al-alloy-based composite." Thesis, University of Oxford, 1995. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.260730.
Повний текст джерелаGupta, Jyoti. "Intergranular stress corrosion cracking of ion irradiated 304L stainless steel in PWR environment." Thesis, Toulouse, INPT, 2016. http://www.theses.fr/2016INPT0031/document.
Повний текст джерелаIASCC is irradiation – assisted enhancement of intergranular stress corrosion cracking susceptibility of austenitic stainless steel. It is a complex degrading phenomenon which can have a significant influence on maintenance time and cost of PWRs’ core internals and hence, is an issue of concern. Recent studies have proposed using ion irradiation (to be specific, proton irradiation) as an alternative of neutron irradiation to improve the current understanding of the mechanism. The objective of this study was to investigate the cracking susceptibility of irradiated SA 304L and factors contributing to cracking, using two different ion irradiations; iron and proton irradiations. Both resulted in generation of point defects in the microstructure and thereby causing hardening of the SA 304L. Material (unirradiated and iron irradiated) showed no susceptibility to intergranular cracking on subjection to SSRT with a strain rate of 5 × 10-8 s-1 up to 4 % plastic strain in inert environment. But, irradiation (iron and proton) was found to increase intergranular cracking severity of material on subjection to SSRT in simulated PWR primary water environment at 340 °C. Correlation between the cracking susceptibility and degree of localization was studied. Impact of iron irradiation on bulk oxidation of SA 304L was studied as well by conducting an oxidation test for 360 h in simulated PWR environment at 340 °C. The findings of this study indicate that the intergranular cracking of 304L stainless steel in PWR environment can be studied using Fe irradiation despite its small penetration depth in material. Furthermore, it has been shown that the cracking was similar in both iron and proton irradiated samples despite different degrees of localization. Lastly, on establishing iron irradiation as a successful tool, it was used to study the impact of surface finish and strain paths on intergranular cracking susceptibility of the material
Hejman, Ulf. "On initiation of chemically assisted crack growth and crack propagation paths of branching cracks in polycarbonate." Licentiate thesis, Malmö högskola, Teknik och samhälle, 2010. http://urn.kb.se/resolve?urn=urn:nbn:se:mau:diva-7790.
Повний текст джерелаКниги з теми "Irradiation assisted stress corrosion cracking"
M, Chung H., Argonne National Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., eds. Irradiation-assisted stress corrosion cracking of model austenitic stainless steel alloys. Washington, DC: U.S. Nuclear Regulatory Commission, 2000.
Знайти повний текст джерелаM, Chung H., Argonne National Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., eds. Irradiation-assisted stress corrosion cracking of model austenitic stainless steel alloys. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2000.
Знайти повний текст джерелаChung, H. M. Irradiation-assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.
Знайти повний текст джерелаChung, H. M. Irradiation-assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.
Знайти повний текст джерелаChung, H. M. Irradiation-assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.
Знайти повний текст джерелаR, Rungta, American Society of Mechanical Engineers. Winter Meeting, American Society of Mechanical Engineers. Pressure Vessels and Piping Division. Materials and Fabrication Section., American Society of Mechanical Engineers. Pressure Vessels and Piping Division. Design and Analysis Committee., and Metal Properties Council, eds. Predictive capabilities in environmentally assisted cracking: Presented at the Winter Annual Meeting of the American Society of Mechanical Engineers, Miami Beach, Florida, November 17-22, 1985. New York, N.Y. (345 E. 47th St., New York 10017): ASME, 1985.
Знайти повний текст джерелаIrradiation-assisted stress corrosion cracking of model austenitic stainless steel alloys. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2000.
Знайти повний текст джерелаEnvironmentally Assisted Cracking: Predictive Methods for Risk Assessment and Evaluation of Materials, Equipment, and Structures (ASTM Special Technical ... (Astm Special Technical Publication// Stp). Astm Intl, 2000.
Знайти повний текст джерелаЧастини книг з теми "Irradiation assisted stress corrosion cracking"
Chung, H. M., W. E. Ruther, R. V. Strain, W. J. Shack, and T. M. Karlsen. "Irradiation-Assisted Stress Corrosion Cracking of Model Austenitic Stainless Steels." In Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 931–39. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2013. http://dx.doi.org/10.1002/9781118787618.ch98.
Повний текст джерелаWang, Mi, Miao Song, Gary S. Was, L. Nelson, and R. Pathania. "Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments Part II: Stress Corrosion Cracking." In The Minerals, Metals & Materials Series, 2177–88. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-030-04639-2_146.
Повний текст джерелаWang, Mi, Miao Song, Gary S. Was, L. Nelson, and R. Pathania. "Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments Part II: Stress Corrosion Cracking." In The Minerals, Metals & Materials Series, 961–72. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-68454-3_70.
Повний текст джерелаHojná, Anna, Miroslava Ernestová, Ossi Hietanen, Ritva Korhonen, Ludmila Hulinová, and Ferenc Oszvald. "Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steel WWER Reactor Core Internals." In Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, 1257–75. Cham: Springer International Publishing, 2011. http://dx.doi.org/10.1007/978-3-319-48760-1_77.
Повний текст джерелаHojná, Anna, Miroslava Ernestová, Ossi Hietanen, Ritva Korhonen, Ludmila Hulinová, and Ferenc Oszvald. "Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steel WWER Reactor Core Internals." In 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 1257–72. Hoboken, New Jersey, Canada: John Wiley & Sons, Inc., 2012. http://dx.doi.org/10.1002/9781118456835.ch131.
Повний текст джерелаFyfitch, Steve, Sarah Davidsaver, and Kyle Amberge. "Irradiation-Assisted Stress Corrosion Cracking Initiation Screening Criteria for Stainless Steels in PWR Systems." In The Minerals, Metals & Materials Series, 2211–20. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-030-04639-2_148.
Повний текст джерелаTeysseyre, S., J. H. Jackson, P. L. Andresen, P. Chou, and B. Carter. "Irradiation Assisted Stress Corrosion Cracking Susceptibility of Alloy X-750 Exposed to BWR Environments." In The Minerals, Metals & Materials Series, 2243–53. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-030-04639-2_151.
Повний текст джерелаMcMurtrey, M. D., and G. S. Was. "Role of Slip Behavior in the Irradiation Assisted Stress Corrosion Cracking in Austenitic Steels." In Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, 1383–95. Cham: Springer International Publishing, 2011. http://dx.doi.org/10.1007/978-3-319-48760-1_85.
Повний текст джерелаMcmurtrey, M. D., and G. S. Was. "Role of Slip Behavior in the Irradiation Assisted Stress Corrosion Cracking in Austenitic Steels." In 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 1383–94. Hoboken, New Jersey, Canada: John Wiley & Sons, Inc., 2012. http://dx.doi.org/10.1002/9781118456835.ch144.
Повний текст джерелаFyfitch, Steve, Sarah Davidsaver, and Kyle Amberge. "Irradiation-Assisted Stress Corrosion Cracking Initiation Screening Criteria for Stainless Steels in PWR Systems." In The Minerals, Metals & Materials Series, 995–1004. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-68454-3_72.
Повний текст джерелаТези доповідей конференцій з теми "Irradiation assisted stress corrosion cracking"
Tanguy, Benoit, Ce´dric Pokor, Anthony Stern, and Philippe Bossis. "Initiation Stress Threshold Irradiation Assisted Stress Corrosion Cracking Criterion Assessment for Core Internals in PWR Environment." In ASME 2011 Pressure Vessels and Piping Conference. ASMEDC, 2011. http://dx.doi.org/10.1115/pvp2011-58051.
Повний текст джерелаRebak, Raul B. "Resistance of Ferritic Steels to Stress Corrosion Cracking in High Temperature Water." In ASME 2013 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/pvp2013-97352.
Повний текст джерелаEason, Ernest D., and Raj Pathania. "Disposition Curves for Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Light Water Reactor Environments." In ASME 2015 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2015. http://dx.doi.org/10.1115/pvp2015-45323.
Повний текст джерелаMatsubara, Toru, and Yuichi Mogami. "Stress Evaluation Method of Baffle Former Bolt and its Maintenance Program." In ASME 2016 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/pvp2016-63971.
Повний текст джерелаLi, Yongkui, Yoshiyuki Kaji, and Takahiro Igarashi. "Study of Weld Residual Stress Field in the Girth Seam H6A of Core Shroud of Boiling Water Reactor." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29269.
Повний текст джерелаElliot, Barry J., Vikram N. Shah, and Yung Y. Liu. "Effective Approaches for Managing Aging Effects in BWR Reactor Coolant System Components for License Renewal." In ASME 2003 Pressure Vessels and Piping Conference. ASMEDC, 2003. http://dx.doi.org/10.1115/pvp2003-2164.
Повний текст джерелаTakakura, Kenichi, Kiyotomo Nakata, Noboru Kubo, Koji Fujimoto, and Kimihisa Sakima. "IASCC Evaluation Method of Irradiated Cold Worked 316SS Baffle Former Bolt in PWR Primary Water." In ASME 2009 Pressure Vessels and Piping Conference. ASMEDC, 2009. http://dx.doi.org/10.1115/pvp2009-77279.
Повний текст джерелаKiss, E. "Component Reliability Considerations for New Designs and Extended Operation of Boiling Water Reactor (BWRs)." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48864.
Повний текст джерелаGe´rard, Robert, and Fre´de´ric Somville. "Situation of the Baffle-Former Bolts in Belgian Units." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75445.
Повний текст джерелаFedorova, Valentina, and Boris Margolin. "Method for Estimation of Pressure Vessel Internals Lifetime on IASCC Criterion." In ASME 2013 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/pvp2013-97949.
Повний текст джерелаЗвіти організацій з теми "Irradiation assisted stress corrosion cracking"
Bell, G. (Irradiation assisted stress corrosion cracking). Office of Scientific and Technical Information (OSTI), April 1990. http://dx.doi.org/10.2172/7010172.
Повний текст джерелаTeysseyre, S. Effect of Swelling on Irradiation-Assisted Stress Corrosion Cracking. Office of Scientific and Technical Information (OSTI), July 2017. http://dx.doi.org/10.2172/1483829.
Повний текст джерелаSimonen, E. P., R. H. Jones, and S. M. Bruemmer. Irradiation-assisted stress corrosion cracking considerations at temperatures below 288{degree}C. Office of Scientific and Technical Information (OSTI), March 1995. http://dx.doi.org/10.2172/46591.
Повний текст джерелаChen, Y., O. K. Chopra, Eugene E. Gruber, and William J. Shack. Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in BWR Environments. Office of Scientific and Technical Information (OSTI), June 2010. http://dx.doi.org/10.2172/1224951.
Повний текст джерелаTeysseyre, Sebastien Paul. Study of the Effect of Swelling on Irradiation Assisted Stress Corrosion Cracking. Office of Scientific and Technical Information (OSTI), September 2016. http://dx.doi.org/10.2172/1364496.
Повний текст джерелаJackson, J. H., S. P. Teysseyre, and M. P. Heighes. Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steel in BWR Conditions. Office of Scientific and Technical Information (OSTI), June 2017. http://dx.doi.org/10.2172/1408502.
Повний текст джерелаGary S. Was. Localized Deformation as a Primary Cause of Irradiation Assisted Stress Corrosion Cracking. Office of Scientific and Technical Information (OSTI), March 2009. http://dx.doi.org/10.2172/950834.
Повний текст джерелаTeysseyre, Sebastien. Irradiation Programs and Test Plans to Assess High-Fluence Irradiation Assisted Stress Corrosion Cracking Susceptibility. Office of Scientific and Technical Information (OSTI), March 2015. http://dx.doi.org/10.2172/1177229.
Повний текст джерелаChen, Y., O. K. Chopra, W. K. Soppet, Nancy L. Dietz Rago, and W. J. Shack. Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels and Alloy 690 from Halden Phase-II Irradiations. Office of Scientific and Technical Information (OSTI), September 2008. http://dx.doi.org/10.2172/1224948.
Повний текст джерелаChung, H. M., and W. J. Shack. Irradiation-assisted stress corrosion cracking behavior of austenitic stainless steels applicable to LWR core internals. Office of Scientific and Technical Information (OSTI), January 2006. http://dx.doi.org/10.2172/915725.
Повний текст джерела