Nuclear energy: current and future schemes

doi:10.1017/CBO9780511718786.016

13 - Nuclear energy: current and future schemes

from Part 2 - Nonrenewable energy sources

Published online by Cambridge University Press: 05 June 2012

Christopher R. Stanek ,

Robin W. Grimes ,

Cetin Unal ,

Stuart A. Maloy and

Sara C. Scott

Edited by

David S. Ginley and

David Cahen

Show author details

Christopher R. Stanek: Affiliation:
Los Alamos National Laboratory, Los Alamos, NM, USA
Robin W. Grimes: Affiliation:
Imperial College London, London, UK
Cetin Unal: Affiliation:
Los Alamos National Laboratory, Los Alamos, NM, USA
Stuart A. Maloy: Affiliation:
Los Alamos National Laboratory, Los Alamos, NM, USA
Sara C. Scott: Affiliation:
Los Alamos National Laboratory, Los Alamos, NM, USA
David S. Ginley: Affiliation:
National Renewable Energy Laboratory, Colorado
David Cahen: Affiliation:
Weizmann Institute of Science, Israel

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Summary

Focus

Nuclear power has been a reliable source of electricity in many countries for decades, and it will be an essential component of the mix of energy sources required to meet environmental goals by reducing greenhouse-gas emissions, reducing the dependence on fossil fuels, and enabling global access to energy. Materials science will play a key role in developing options in nuclear power, including new reactors with improved safety (especially in the light of the Fukushima Daiichi nuclear accident), reliability, and efficiency; technology to help minimize proliferation (discussed in Chapter 14); and viable, safe, long-term options for waste management (discussed in Chapter 15). Such efforts will provide opportunities to address broader challenges associated with nuclear energy, including public opinion and the investment risks associated with building new nuclear power plants.

Synopsis

The energy density (i.e., the quantity of useful energy stored per unit volume) of uranium fuel used today in light-water reactors (the most prevalent type of nuclear reactor) is already orders of magnitude larger than that of other energy sources. For example, one reactor fuel pellet produces approximately as much heat energy as 150 gal of fuel oil or 1 ton of high-grade coal. Moreover, the utilization of the energy density is being increased further through improvements in fuel technology and by developments in reactor design. This chapter focuses on the materials science challenges that exist in a fission reactor, that is, those related to the nuclear fuel, the cladding, and the structural materials, which are exposed to extremely high temperatures, moderate pressures, and an intense radiation field. Technical issues that extend beyond the workings of reactors, namely nuclear non-proliferation and nuclear waste, are addressed in Chapters 14 and 15, respectively.

Type: Chapter
Information: Fundamentals of Materials for Energy and Environmental Sustainability , pp. 147 - 161

DOI: https://doi.org/10.1017/CBO9780511718786.016 [Opens in a new window]

Publisher: Cambridge University Press

Print publication year: 2011

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References

Hahn, O.Strassmann, F. 1938 “Concerning the existence of alkaline earth metals resulting from neutron irradiation of uranium,”Naturwissenschaften 26 755CrossRef Google Scholar

Meitner, L.Frisch, O. R. 1939 “Disintegration of uranium by neutrons: a new type of nuclear reaction,”Nature 143 239CrossRef Google Scholar

Fermi, E. 1946 “The development of the first chain reaction pile,”Proc. Am. Phil. Soc 90 20Google Scholar

Arnold, L. 1992 Windscale 1957. Anatomy of a Nuclear AccidentNew YorkSt. Martin's PressCrossRef Google Scholar

Finn, P. 2005 Chernobyl's Harm Was Far Less Than Predicted, U.N. Report SaysWashington PostGoogle Scholar

European Nuclear Societyhttp://www.euronuclear.org/info/encyclopedia/n/nuclear-power-plant-world-wide.htm

Lester, R K.Rosner, R. 2009 “The growth of nuclear power: drivers & constraints,”Daedalus 138 19CrossRef Google Scholar

Bohr, N.Wheeler, J. A. 1939 “The mechanism of nuclear fission,”Phys. Rev 56 426CrossRef Google Scholar

US DOE 2010 Nuclear Energy Research and Development Roadmap, A Report to CongressUS Department of Energy, Nuclear EnergyGoogle Scholar

IAEA 2005 Country Nuclear Fuel Cycle ProfilesViennaIAEAGoogle Scholar

Grimes, R. W.Nuttal, W. J. 2010 “Generating the option of a two-stage nuclear renaissance,”Science 329 799CrossRef Google Scholar

MIT 2010 The Future of the Nuclear Fuel Cycle, An Interdisciplinary MIT StudyCambridge, MAMassachusetts Institute of TechnologyGoogle Scholar

Murray, R. L. 2001 Nuclear Energy. An Introduction to the Concepts, Systems, and Applications of Nuclear ProcessesBoston, MAButterworth HeinemannGoogle Scholar

Denniss, I. S.Jeapes, A. P. 1996 “Reprocessing irradiated fuel,”The Nuclear Fuel Cycle, From Ore to Waste,”Wilson, P. D.OxfordOxford University Press116Google Scholar

Sheffield, R. L.Pitcher, E. J. 2009 Application of Accelerators in Nuclear Waste ManagementInternational Committee for Future Accelerators NewsletterGoogle Scholar

Duderstadt, J. J.Hamilton, L. J. 1976 Nuclear Reactor AnalysisNew YorkWileyGoogle Scholar

Todreas, N. E.Kazimi, M. 1989 Nuclear Systems Volume I: Thermal Hydraulic FundamentalsNew YorkHemisphereGoogle Scholar

Todreas, N. E.Kazimi, M. 1989 Nuclear Systems Volume II: Elements of Thermal Hydraulic DesignNew YorkHemisphereGoogle Scholar

Lamarsh, J. R.Baratta, A. J. 2001 Introduction to Nuclear EngineeringEnglewood Cliffs, NJPrentice HallGoogle Scholar

Cochran, T. B.Feiveson, H. A.Patterson, W. 2010 Fast Breeder Reactor Programs; History and StatusInternational Panel on Fissile MaterialsGoogle Scholar

Gougar, H. D.Petti, D. A.Wright, R. N. 2010

Buckthorpe, D. 2009 “Materials for the Very High Temperature Reactor – results and progress within the Fifth and Sixth Framework Programmes,”Adv. Mater. Res 59 243CrossRef Google Scholar

Petti, D.Abram, T.Hobbins, R.Kendall, J. 2010

Ingersoll, D. T. 2009 “Deliberately small reactors and the second nuclear era,”Prog. Nucl. Energy 51 589CrossRef Google Scholar

Naus, D. J. 2009 “The management of aging in nuclear power plant concrete structures,”JOM 61 35CrossRef Google Scholar

Grimes, R. W.Konings, R. J. M.Edwards, L. 2008 “Greater tolerance for nuclear materials,”Nature Mater 7 683CrossRef Google Scholar

Was, G. S. 2007 “Role of irradiation in stress corrosion cracking,”Radiation Effects in SolidsSickafus, K.Kotomin, E. A.Uberuaga, B. P.New YorkSpringer421CrossRef Google Scholar

Yang, R.Cheng, B.Deshon, J.Edsinger, K.Ozer, O. 2006 “Fuel R & D to improve fuel reliability,”J. Nucl. Sci. Technol 43 951CrossRef Google Scholar

Brinkman, J. A. 1956 “Production of atomic displacements by high-energy particles,”Am. J. Phys 24 251CrossRef Google Scholar

Seitz, F. 1952 “Imperfections in nearly perfect crystals: a synthesis,”Imperfections in Nearly Perfect CrystalsShockley, W.New YorkWiley3Google Scholar

Demkowicz, M. J.Hoagland, R. G.Hirth, J. P. 2008 “Interface structure and radiation damage resistance in Cu–Nb multilayer nanocomposites,”Phys. Rev. Lett 100 136102CrossRef Google Scholar

Zinkle, S. J.Busby, J. T. 2009 “Structural materials for fission and fusion energy,”Mater. Today 12 12CrossRef Google Scholar

Odette, G. R.Alinger, M. J.Wirth, B. D. 2008 “Recent developments in irradiation-resistant steels,”Ann. Rev. Mater. Sci 38 471CrossRef Google Scholar

Allen, T. R.Burlet, H.Nanstad, R. K.Samaras, M.Ukai, S. 2009 “Advanced structural materials and cladding,”MRS Bull 34 20CrossRef Google Scholar

Allen, T. R.Busby, J. T.Klueh, R. L.Maloy, S. A.Toloczko, M. B. 2008 “Cladding and duct materials for advanced nuclear recycle reactors,”JOM 60 15CrossRef Google Scholar

Garner, F. A. 1996 “Irradiation performance of cladding and structural steels in liquid metal reactors,”Nuclear MaterialsFrost, B. R. T.WeinheimVCH Verlagsgesellschaft mbH420Google Scholar

Sickafus, K. E. 2007 “Radiation-induced amorphization resistance and radiation tolerance in structurally related oxides,”Nature Mater 6 217CrossRef Google Scholar

Kleykamp, H. 1985 “The chemical state of the fission products in oxide fuels,”J. Nucl. Mater 131 221CrossRef Google Scholar

Matzke, H. 1980 “Gas relase mechanisms in UO2 – a critical review,”Radiat. Effects Defects Solids 53 219CrossRef Google Scholar

Manara, D.Ronchi, C.Sheindlin, M.Lewis, M.Brykin, M. 2005 “Melting of stoichiometric and hyperstoichiometric uranium dioxide,”J. Nucl. Mater 342 148CrossRef Google Scholar

Wirth, B. D. 2007 “How does radiation damage materials?,”Science 318 923CrossRef Google Scholar

Bai, X. M.Voter, A. F.Hoagland, R. G.Nastasi, M.Uberuaga, B. P. 2010 “Efficient annealing of radiation damage near grain boundaries via interstitial emission,”Science 327 1631CrossRef Google Scholar

Carroll, R. M.Sisman, O. 1966 “Fission-gas release during fissioning in UO2,”Nucl. Appl 2 142CrossRef Google Scholar

Olander, D. R. 1976 Fundamental Aspects of Nuclear Reactor Fuel ElementsSpringfield, VA, US Department of CommerceCrossRef Google Scholar

Devanathan, R.Van Brutzel, L.Chartier, A. 2010 “Modeling and simulation of nuclear fuel materials,”Energy Environ. Sci 3 1406CrossRef Google Scholar

Stan, M. 2009 “Discovery and design of nuclear fuels,”Mater. Today 12 20CrossRef Google Scholar

Catlow, C. R. A. 1978 “Fission gas diffusion in uranium dioxide,”Proc. Roy. Soc. Lond. A 364 473CrossRef Google Scholar

Grimes, R. W.Catlow, C. R. A. 1991 “The stability of fission products in uranium dioxide,”Phil. Trans. Roy. Soc. Lond. A 335 601CrossRef Google Scholar

van Brutzel, L.Vincent-Aublant, E. 2008 “Grain boundary influence on displacement cascades in UO2: a molecular dynamics study,”J. Nucl. Mater 377 522CrossRef Google Scholar

Freyss, M.Petit, T.Crocombette, J. P. 2005 “Point defects in uranium dioxide: pseudopotential approach in the generalized gradient approximation,”J. Nucl. Mater 247 44CrossRef Google Scholar

Andersson, D. A.Lezama, J.Uberuaga, B. P.Deo, C.Conradson, S. D. 2009 “Cooperativity among defect sites in AO2+ and A4O9 (A = U, Np, Pu): density functional calculations,”Phys. Rev. B 79 0241100CrossRef Google Scholar

Stoller, R. E.Odette, G. R.Wirth, B. D. 1997 “Primary damage formation of BCC iron,”J. Nucl. Mater 251 49CrossRef Google Scholar

Andersson, D. A.Wantanabe, T.Deo, C.Uberuaga, B. P. 2009 “Role of di-interstitial clusters in oxygen transport in UO2+ from first principles,”Phys. Rev. B 80CrossRef Google Scholar

Stan, M.Ramirez, J. C.Cristea, P. 2007 “Models and simulations of nuclear fuel materials properties,”J. Alloys Comp 444 415CrossRef Google Scholar

Millet, P. C.Rokkam, S.El-Azab, A.Tonks, M.Wolf, D. 2009 “Void nucleation and growth in irradiated polycrystalline metals: a phase-field model,”Modelling Simul. Mater. Sci. Eng 17 064003CrossRef Google Scholar

Newman, C.Hansen, G.Gaston, D. 2009 “Three dimensional coupled simulation of thermomechanics, heat, and oxygen diffusion in UO2 nuclear fuel rods,”J. Nucl. Mater 392 6CrossRef Google Scholar

Andersson, D. A.Uberuaga, B. P.Nerikar, P. V.Unal, C.Stanek, C. R. 2011 2±

Nerikar, P. V.Rudman, K.Desai, T. G. 2011

Nerikar, P. V.Parfitt, D. C.Andersson, D. A. 2011

Parfitt, D.Bishop, C. L.Wenman, M. R.Grimes, R. W.“Strain fields and line energies of dislocations in uranium dioxide,”J. Phys. – Condens. Matter 22 2010 175004CrossRef Google Scholar

Carmack, J. 2010 Advanced Fuels Separate Effects Tests R&D PlanUS Department of EnergyGoogle Scholar

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