MATERIAL ISSUES FOR CURRENT AND ADVANCED NUCLEAR REACTOR DESIGNS
DOI:
https://doi.org/10.7251/COMEN1401010HAbstract
In all engineering applications, design and materials together determine the functionality and reliability of a device. This is particularly important in nuclear systems where the materials are pushed to their limits and phenomena not present anywhere else occur. In nuclear systems a combination of high temperature and pressure, stress, corrosive environment and high radiation environment combined causes significant materials challenges. Majority of commercial LWRs today are licensed for 40 years of operation, but many of them undergo lifetime extension to 60 or possibly 80 years. Materials degradation has always been a significant issue. However, due to the lifetime plant extension, finding materials that could sustain prolonged exposure to these extreme conditions has become a significant problem. In addition to the materials challenges in current LWRs, advanced reactors usually deal with even more difficult issues due to their operational requirements. Unusual heat transport media, such as liquid metals, liquid salts or other types of coolants, lead to a whole new set of material challenges. While corrosion has been the main issue, much higher operating temperatures create additional difficulties. In this paper, we present an overview of materials issues for current and advanced nuclear reactor designs.References
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[3] IAEA-PRIS (Power Reactor Information System) http://www.iaea.org/PRIS/home.aspx
[4] Technology Roadmap – Nuclear Energy, Nuclear Energy Agency (NEA) and International Energy Agency (IEA), 2010. Available at http://www.iea.org/roadmaps/
[5] Resources and Statistics: Nuclear Statistics, Nuclear Energy Institute, Available at http://www.nei.org/resourcesandstats/nuclear_statistics/ (accessed in August 2011).
[6] A Technology Roadmap for Generation IV Nuclear Energy Systems, Issued by the U.S. DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum, December 2002.
[7] E. Cummins, Intelligent Design and Implementation of Nuclear Power for Carbon Free Energy: The Westinghouse AP1000, Presentation at CITRUS, The University of California at Berkeley, 2010.
[8] M. Haitzmann and L. Van Den Durpel, AREVA’s Research & Development, Paris, France, July 10, 2012.
[9] Source Book: Soviet-Designed Nuclear Power Plants in Russia, Ukraine, Lithuania, Armenia, the Czech Republic, the Slovak Republic, Hungary and Bulgaria, Fifth Edition, Nuclear Energy Institute – NEI, Washington, D.C., 1997.
[10] Advanced Reactor Information System (ARIS), International Atopic Energy Agency, aris.iaea.org
[11] J. Vujic, R. M. Bergmann, R. Skoda,
M. Miletic, Small modular reactors: Simpler, safer, cheaper?, Energy: The International Journal (Elsevier), Vol. 45−1 (2012) 288−295.
[12] D. M. Carelli, L. E. Conway , L. Oriani, B. Petrovic, C. V. Lombardi, M. E. Ricotti , et al. The design and safety features of the IRIS reactor, Nuclear Engineering and Design, Vol. 230−1−3 (2004) 151−167.
[13] http://gehitachiprism.com/what-is-prism/how-prism-works/
[14] http://www.nuscalepower.com/overviewofnuscalestechnology.aspx
[15] http://www.babcock.com/products/Pages/mPower-Reactor.aspx
[16] Pellet-clad Interaction in Water Reactor Fuels; Report OECD NEA 2005.
[17] D. Wongsawaeng, D. Olander, Liquid-Metal Bond for LWR Fuel Rods, American Nucl Technl., Vol. 159 (2007) 279−291.
[18] Nuclear Fuel Behaviour in Loss of Coolant accidents (LOCA) conditions, State-of-the-art Reort, OECD 2009, https://www.oecd-nea.org/nsd/reports/2009/nea6846_LOCA.pdf,
[19] A. L. Camp, J. C. Cummings, M. P. Sherman, C. F. Kupiec, R. J. Healy, J. S. Caplan,
J. R. Sandhop, J. H. Saunders, Light Water reactor hydrogen manual NRC report NUREG/CR-2726 1983, http://pbadupws.nrc.gov/docs/ML0716/ML071620344.pdf.
[20] L. Ammirabile, S. P. Walker, Multi-pin modelling of PWR fuel pin ballooning during post-LOCA reflood, Nucl. Eng Design, Vol. 238 (2008) 1448−1458.
[21] Y. Katoh, L. L. Snead, C. H. Henager Jr, A. Hasegawa, A. Kohyama, B. Riccardi, H. Hegeman, Current status and critical issues for development of SiC composites for fusion applications, J. Nucl. Mater., Vol. 367−370 (2007) 659−671.
[22] U. Linus, T. Ogbujii, A pervasive mode of oxidative degradation in a SiC–SiC composite, J. Amer., Cermaic Soc., Vol. 81 (1998) 2777−2784.
[23] Regulatory Guide 1.99-Rev 2: Radiation Embrittlement to Reactor Pressure Vessel Materials (Washington, D.C.: U.S. Government Printing Office, U.S. Nuclear Regulatory Commission, 1988).
[24] G. R. Odette and G.E. Lucas, Irradiation Embrittlement of Reactor Pressure Vessel Steels: Mechanisms, Models and Data Correlations, Radiation Embrittlement of Reactor Pressure Vessel Steels−An International Review, ASTM STP 909, ed. L. E. Steele (Philadelphia, PA: ASTM, 1986), pp. 206–241.
[25] G. R. Odette, G. E. Lucas, Embrittlement of Nuclear Reactor Pressure Vessels, JOM, Vol. 53 (2001) 18−22.
[26] Report on Aging of Nuclear Power Plant Reinforced Concrete Structures, D. J. Naus, C. B. Oland, B. R. Ellingwood, NUREG/CR-6424
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[28] S. J. Zinkle, OECD New Workshop on Structural Materials
for Innovative Energy Systems, Karlsruhe Germany June 2007.
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[30] M. J. Hackett, J. T. Busby, M. K. Miller, G. S. Was, Effects of oversized solutes on radiation-induced segregation in austenitic stainless steels, J. Nucl. Mat., Vol. 389−2 (2009) 265−278.
[31] M. Kondo, T. Nagasaka, A. Sagara,
N. Noda, T. Muroga, Q. Xu, M. Nagura, A. Suzuki, T. Terai, Metallurgical study on corrosion of austenitic steels in molten soft LiF-BeF2, Journal of Nuclear Materials, Vol. 386–388 (2009) 685–688.
[32] L. C. Olson, J. W. Ambrosek, K. Sridharan, M. H. Anderson, T. R. Allen, Materials corrosion in molten LiF-NaF-KF salt, Journal of Fluorine Chemistry, Vol. 130−1 (2009) 67–73.
[33] M. G. Barker, D. J. Wood, The corrosion of chromium, iron, and stainless steel in liquid sodium, J. of the Less Common Metals, Vol. 35 (1974) 315–323.
[34] J. Zhang, N. Li, Review of the studies on fundamental issues in LBE corrosion, J. Nucl. Mat., Vol. 373 (2008) 351–377.
[35] G. Mueller, A. Heinzel, G. Schumacher, A. Weisenburger, Control of oxygen concentration in liquid lead and lead bismuth, Journal of Nuclear Materials, Vol. 321 (2003) 256–262.
[36] P. Hosemann, M E Hawley, D. Koury, J. Welch, A. L. Johnson, G. Mori, S. A. Maloy, Nanoscale characterization of HT-9 exposed to lead bismuth eutectic at 550 °C for 3000 h, J. Nucl Mat., Vol. 381 (2008) 211−215.
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[38] P. Hosemann, R Dickerson, P Dickerson, N Li, SA Maloy, Transmission Electron Microscopy (TEM) on Oxide Layers formed on D9 stainless steel in Lead Bismuth Eutectic (LBE), Corrosion Science, Vol. 66 (2013) 196–202.
[39] J. Zhang, P. Hosemann, S. A. Maloy, Models of liquid metal corrosion, J. Nucl. Mat., Vol. 404−1 (2010) 82−96.
[40] N. Bailey, P. Hosemann, Private correspondence.
[41] J. Van den Bosch, P. Hosemann, A. Almazouzi, S. Maloy, Liquid metal embrittlement of silicon enriched steel for nuclear applications, J. Nucl. Mat., Vol. 389, (2010) 116-121.
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[43] K. G. E. Brenner, L.W. Graham, The Development and Application of a Unified Corrosion Model for High-Temperature Gas-Cooled Reactor Systems, Nucl Tech., Vol. 66 (1984) 404−414.
[44] O. Anderoglu, J. Van den Bosch, P. Hosemann, E. Stergar, B.H. Sencer, D. Bhattacharyya, R. Dickerson, P. Dickerson, M. Hartl, S. A. Maloy, Phase stability of an HT-9 duct irradiated in FFTF, J. Nuc. Mat., Vol. 430 (2012) 194–204.
[45] T. Tanaka, K. Oka, S. Ohnuki, S. Yamashita, T. Suda, S. Watanabe, E. Wakai, Synergistic effect of helium and hydrogen for defect evolution under multi-ion irradiation of Fe–Cr ferritic alloys, J. Nucl. Mater., Vol. 329–333 (2004) 294−298.
[46] P. Hosemann, Y. Dai, E. Stergar, H. Leitner, E. Olivas, A.T. Nelson, S.A. Maloy, Large and Small Scale Materials Testing of HT-9 Irradiated in the STIP Irradiation Program, Exp. Mech., Vol. 51 (2011) 1095−1102.
[47] P. Hosemann, E. Stergar, P. Lei, Y. Dai, S.A.MaloyM. A. Pouchon, K. Shiba, D. Hamaguchi, H. Leitner, Macro and microscale mechanical testing and local electrode atom probe measurements of STIP irradiated F82H, Fe–8Cr ODS and Fe–8Cr–2W ODS, J. Nucl. Mat., Vol. 417 (2011) 274−278.
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2014-09-24
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