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Nuclear Power Plants

  • Bahman Zohuri
  • Patrick McDaniel
Chapter

Abstract

Currently, about half of all nuclear power plants are located in the United States. There are many different kinds of nuclear power plants, and we will discuss a few important designs in this text. A nuclear power plant harnesses the energy inside atoms themselves and converts this to electricity. All of us use this electricity. In Sect. 18.1 of this chapter, we show you the idea of the fission process and how it works. A nuclear power plant uses controlled nuclear fission. In this chapter, we will explore how a nuclear power plant operates and the manner in which nuclear reactions are controlled. There are several different designs for nuclear reactors. Most of them have the same basic function, but one’s implementation of this function separates it from another. There are several classification systems used to distinguish between reactor types. Below is a list of common reactor types and classification systems found throughout the world, and they are briefly explained down below according to three types of classification either (1) classified by moderator material, (2) classified by coolant material, or (3) classified by reaction type.

Bibliography

  1. 1.
  2. 2.
    B.L. Cohen, Breeder reactors: A renewable energy source. Am. J. Phys. 51, 1 (1983)Google Scholar
  3. 3.
    A. Weinberg, The Second Fifty Years of Nuclear Fission, in Proc. Special Symposium: 50 Years of Nuclear Fission in Review, Ontario, Canada, June 5, 1989, Canadian Nuclear SocietyGoogle Scholar
  4. 4.
    N. Seko, Aquaculture of uranium in seawater by a fabric-adsorbent submerged system. Nucl. Technol. 144, 274 (2003)CrossRefGoogle Scholar
  5. 5.
    Some Physics of Uranium. Available on the Internet at http://www.worldnuclear.org/education/phys.html (December 2005)
  6. 6.
    W.H. Hannum, The Technology of the Integral Fast Reactor and its Associated Fuel Cycle. Prog. Nucl. Energy 31, 1 (1997)CrossRefGoogle Scholar
  7. 7.
  8. 8.
  9. 9.
    World Nuclear Association website. http://www.world-nuclear.org/
  10. 10.
    IAEA Power Reactor Information System website. http://www.iaea.org/programmes/a2/
  11. 11.
  12. 12.
    Sustainable Nuclear Energy Technology Platform, Strategic Research Agenda, May 2009, www.SNETP.eu
  13. 13.
    Nuclear Energy Outlook 2008, OECD/NEA Report No. 6348, 2008, Nuclear Energy Agency, ParisGoogle Scholar
  14. 14.
    2009 Update of the MIT 2003 Future of Nuclear Power, An Interdisciplinary MIT Study, 2003, Massachusetts Institute of Technology, Cambridge USA, May 2009. http://web.mit.edu/nuclearpower/pdf/nuclearpower-update2009.pdf
  15. 15.
    Projected Costs of Generating Electricity, 2005 Update, NEA/OECD, 2005Google Scholar
  16. 16.
    The Future of Nuclear Power – The Role of Nuclear Power in a Low Carbon UK Economy, Consultation Document, 2007, DTI, UK. http://www.berr.gov.uk/files/file39197.pdf
  17. 17.
    Uranium 2007: Resources, production and demand. OECD nuclear energy agency and the International Atomic Energy Agency, OECD 2008 NEA N 6345Google Scholar
  18. 18.
    Strategic and Policy Issues Raised by the Transition from Thermal to Fast Nuclear Systems, 2009, OECD/NEA report no. 6352Google Scholar
  19. 19.
    A Technology Roadmap for Generation IV Nuclear Energy Systems, 2002, GIF-002 - 00, Issued by the US DoE and the Generation IV International Forum. http://www.gen-4.org/PDFs/GenIVRoadmap.pdf
  20. 20.
    Proposal for a COUNCIL DIRECTIVE (EURATOM) setting up a Community framework for nuclear safety COM(2008) 790/3, November 2008Google Scholar
  21. 21.
    COUNCIL OF THE EUROPEAN UNION Legislative Acts and Other Instruments 10667/09, June 2009Google Scholar
  22. 22.
  23. 23.
    Updated Emissions Projections, July 2006, DTI. http://www.dti.gov.uk/files/file31861.pdf
  24. 24.
    DTI: Energy White Paper, Meeting the Energy Challenge. http://www.dti.gov.uk/energy/whitepaper
  25. 25.
  26. 26.
  27. 27.
  28. 28.
    A.K. Raja, Amit Prakash Srivastava, Manish Dwivedi, “Power Plant Engineering”, New Age International (P) Limited, Publishers, 2006Google Scholar
  29. 29.
    L. Mathieu, D. Heuer, E. Merle-Lucotte, et al., Possible configurations for the thorium molten salt reactor and advantages of the fast non-moderated version. Nucl Sci Eng 161, 78–89 (2009)CrossRefGoogle Scholar
  30. 30.
    C.W. Forsberg et al., in Liquid Salt Applications and Molten Salt Reactors, Revue Générale du Nucléaire N° 4/2007, 63 (2007)Google Scholar
  31. 31.
    E. Merle-Lucotte, D. Heuer et al., Introduction of the Physics of Molten Salt Reactor, Materials Issues for Generation IV Systems, NATO Science for Peace and Security Series B, Editions Springer, 501–521 (2008)Google Scholar
  32. 32.
    E. Merle-Lucotte, D. Heuer et al., Minimizing the Fissile Inventory of the Molten Salt Fast Reactor, in Proceedings of the Advances in Nuclear Fuel Management IV (ANFM 2009), Hilton head Island, USA (2009)Google Scholar
  33. 33.
    C. Renault, M. Hron, R. Konings, D.E. Holcomb, The molten salt reactor (MSR) in generation IV: Overview and perspectives, in GIF Symposium Proceeding, (Paris, France, 2009)Google Scholar
  34. 34.
    V. Ignatiev et al., Characteristics of molten salt actinide recycler and transmuter system, in Proceedings of International Conference on Emerging Nuclear Energy Systems, Brussels, Belgium, 21–26 August: paper ICQ064 (2005)Google Scholar
  35. 35.
    ISTC# 1606 final report, International scientific technical centre, Moscow, July, 2007Google Scholar
  36. 36.
    C.W. Forsberg, P.F. Peterson and R.A. Kochendarfer, Design options for the advanced high-temperature reactor?, in Proc. 2008 International Congress on Advances in Nuclear Power Plants (ICAPP?08), Anaheim, CA USA, June 8–12, 2008Google Scholar
  37. 37.
    Ph. Bardet et al., Design, Analysis and Development of the Modular PB-AHTR, in Proc. 2008 International Congress on Advances in Nuclear Power Plants (ICAPP?08), Anaheim, CA USA, June 8–12, 2008Google Scholar
  38. 38.
    V. Ignatiev, A. Surenkov, Material performance in molten salts. Compr Nucl Mater 5, 221–250 (2012)CrossRefGoogle Scholar
  39. 39.
    O. Bene, R.J.M. Konings, Molten salt reactor fuel and coolant. Compr Nucl Mater 3, 359–389 (2012)CrossRefGoogle Scholar
  40. 40.
    E. Merle-Lucotte, D. Heuer, M. Allibert, M. Brovchenko, N. Capellan, and V. Ghetta, Launching the thorium fuel cycle with the molten salt fast reactor, Contribution 11190, International Congress on Advances in Nuclear Power Plants (ICAPP), Nice, France (2011)Google Scholar
  41. 41.
    E. Merle-Lucotte, D. Heuer, M. Allibert, X. Doligez, V. Ghetta, Optimizing the Burning Efficiency and the Deployment Capacities of the Molten Salt Fast Reactor?, Contribution 9149, Global 2009, The Nuclear Fuel Cycle: Sustainable Options & Industrial Perspectives, Paris, France (2009)Google Scholar
  42. 42.
    Doligez et al., Numerical tools for Molten Salt Reactors simulations, in Proceedings of the International Conference Global 2009 – The Nuclear Fuel Cycle: Sustainable Options & Industrial Perspectives, Paris, France (2009)Google Scholar
  43. 43.
    E. Merle-Lucotte, D. Heuer, M. Allibert, X. Doligez, V. Ghetta, Simulation Tools and New Developments of the Molten Salt Fast Reactor, Contribution A0115, European Nuclear Conference ENC2010, Barcelone, Espagne (2010)Google Scholar
  44. 44.
    M. Brovchenko, D. Heuer, E. Merle-Lucotte, M. Allibert, N. Capellan, V. Ghetta, A. Laureau, Preliminary safety calculations to improve the design of Molten Salt Fast Reactor, PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tennessee, USA, April 15–20, 2012, on CD-ROMGoogle Scholar
  45. 45.
    S. Delpech, E. Merle-Lucotte, T. Augé, D. Heuer, MSFR: Material issued and the effect of chemistry control, Generation IV International Forum Symposium, Paris, France (2009)Google Scholar
  46. 46.
    M. Beilmann, O. Bene, R.J.M. Konings, T. Fanghänel, Thermodynamic assessment of the (LiF + UF3) and (NaF + UF3) systems. J. Chem. Thermodyn. 57, 22–31 (2013)CrossRefGoogle Scholar
  47. 47.
    O. Bene, M. Beilmann, R.J.M. Konings, Thermodynamic assessment of the LiF-NaF-ThF4-UF4. J. Nucl. Mater. 405(2), 186–198 (2010)CrossRefGoogle Scholar
  48. 48.
    S. Delpech, E. Merle-Lucotte, D. Heuer, M. Allibert, V. Ghetta, C. Le-Brun, L. Mathieu, G. Picard, Reactor physics and reprocessing scheme for innovative molten salt reactor system. J Fluor Chem 130(1), 11–17 (2009)CrossRefGoogle Scholar
  49. 49.
    S. Jaskierowicz, S. Delpech, P. Fichet, C. Colin, C. Slim and G. Picard, Pyrochemical Reprocessing of Thorium-Based Fuel, in Proceeding of ICAPP2011, Nice, France (2011)Google Scholar
  50. 50.
    V. Ignatiev et al., Molten salt reactor: new possibilities, problems and solutions. At Energ 112(3), 135 (2012)CrossRefGoogle Scholar
  51. 51.
    V. Ignatiev, et al, Progress in Development of MOSART Concept with Th Support, ICAPP?12, Chicago, USA, June 24–28, 2012, Paper No. 12394Google Scholar
  52. 52.
    V. Afonichkin, A. Bovet, V. Shishkin, Salts purification and voltammetric study of the electro reduction of U(IV) to U(III) in molten LiF–ThF4. J. Nucl. Mater. 419(1–3), 347 (2011)CrossRefGoogle Scholar
  53. 53.
    F. Baque, K. Paumel, G. Cornloup, M.A. Ploix and J.M. Augem, Non-destructive Examination of Immersed Structures within Liquid Sodium, ANIMMA 2011, Ghent, June 6–9 (2011)Google Scholar
  54. 54.
    Y.S. Joo, C.G. Park, J.B. Kim, S.H. Lim, Development of ultrasonic waveguide sensor for under-sodium inspection in a sodium-cooled fast reactor. NDT&E Int 44, 239–246 (2011)CrossRefGoogle Scholar
  55. 55.
    J. Floyd, N. Alpy, D. Haubensack, G. Avakian, G. Rodriguez, On-design efficiency reference charts for the supercritical CO2 Brayton cycle coupled to a SFR, in Proc. ICAPP2011, Nice, France, 2–5 May, 2011, Paper 11054Google Scholar
  56. 56.
    A. Moisseytsev, J.J. Sienicki, Dynamic simulation and control of the S-CO2 cycle: From full power to decay heat removal, in Proc. ATH ?12, Embedded Topical Meeting of ANS 2012 Winter Meeting, San Diego, CA, USA, 11–15 November, 2012, Paper 6461Google Scholar
  57. 57.
    J.J. Sienicki. et. al., Synthesis of results obtained on sodium components and technology through the generation IV international forum SFR component design and balance-of-plant project, in Proc. FR13, Paris, France, 4–7, March, 2013Google Scholar
  58. 58.
    F. Delage et al., Status of advanced fuel candidates for Sodium Fast Reactor within the Generation IV International Forum, J. of Nuclear Materials, NUMA46668 (to be published), 2013Google Scholar
  59. 59.
    Y. Oka, S. Koshizuka, Y. Ishiwatari, A. Yamaji, Super Light Water Reactors and Super Fast Reactors (Springer, New York, 2010)Google Scholar
  60. 60.
    K. Yamada, S. Sakurai, Y. Asanuma, R. Hamazaki, Y. Ishiwatari, K. Kitoh, Overview of the Japanese SCWR concept developed under the GIF collaboration, in Proc. ISSCWR-5, Vancouver, Canada, March 13–16, 2011Google Scholar
  61. 61.
    T. Schulenberg, J. Starflinger, High Performance Light Water Reactor ? Design and Analyses (KIT Scientific Publishing, New York, 2012)Google Scholar
  62. 62.
    M. Yetisir, W. Diamond, L.K.H. Leung, D. Martin, R. Duffey, Conceptual Mechanical Design for A Pressure-Tube Type Supercritical Water-Cooled Reactor, in Proc. 5th International Symposium on Supercritical Water-cooled Reactors, Vancouver, Canada, March 13–17, 2011Google Scholar
  63. 63.
    S.B. Ryzhov, V.A. Mokhov, M.P. Nikitenko, A.K. Podshibyakin, I.G. Schekin, A.N. Churkin, Advanced designs of VVER reactor plant, The 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8), October 10–14, 2010, Shanghai, China, Paper N8P0184Google Scholar
  64. 64.
    S.B. Ryzhov, P.L. Kirillov, et al., Concept of a single-circuit RP with vessel type supercritical water-cooled reactor, in Proc. ISSCWR-5, Vancouver, Canada, March 13–16, 2011Google Scholar
  65. 65.
    I.L. Pioro, R.B. Duffey, Heat Transfer and Hydraulic Resistance at Supercritical Pressures in Power Engineering Applications (ASME Press, New York, 2007)Google Scholar
  66. 66.
    J. Kaneda, S. Kasahara, F. Kano, N. Saito, T. Shikama, H. Matsui, Material development for supercritical water-cooled reactor, in Proc. ISSCWR-5, Vancouver, Canada, March 13–16, 2011Google Scholar
  67. 67.
    D. Guzonas, F. Brosseau, P. Tremaine, J. Meesungnoen, J.-P. Jay-Gerin, Water chemistry in a supercritical water? Cooled pressure tube reactor. Nucl. Technol. 179, 205–219 (2012)CrossRefGoogle Scholar
  68. 68.
  69. 69.
  70. 70.
    R. Stainsby, J.C Garnier, P. Guedeney, K. Mikityuk, T. Mizuno, C. Poette, M. Pouchon, M. Rini, J. Somers, E. Touron,The Generation IV Gas-cooled Fast Reactor. Paper 11321, Proc. ICAPP 2011 Nice, France, 2–5 May 2011Google Scholar
  71. 71.
    Z. Perkó, J.L. Kloosterman, S. Fehér, Minor actinide transmutation in GFR600. Nucl. Technol. 177, 83–97 (2012)CrossRefGoogle Scholar
  72. 72.
    R. Stainsby, K. Peers, C. Mitchell, C. Poette, K. Mikityuk, J. Somers, Gas cooled fast reactor research in Europe? Nucl. Eng. Des. 241, 3481–3489 (2011)CrossRefGoogle Scholar
  73. 73.
    A. Epiney, N. Alpy, K. Mikityuk, R. Chawla, A standalone decay heat removal device for the gas-cooled fast reactor for intermediate to atmospheric pressure conditions. Nucl. Eng. Des. 242, 267–284 (2012)CrossRefGoogle Scholar
  74. 74.
    R.R. Smith, D.W. Cissei, Fast Reactor Operation in the United States, in International Symposium on Design, Construction, and Operating Experience of Demonstration LMFBRs, Bologna, Italy, April 10–14, 1978Google Scholar
  75. 75.
    U.S. Nuclear energy research advisory committee (NERAC) and the generation IV international forum (GIF), Generation IV technology roadmap, Report GIF-002-00, December 2002Google Scholar
  76. 76.
    A.E. Waltar, D.R. Todd, P.V. Tsvetkov, Fast Spectrum Reactors (Springer, New York, 2012)CrossRefGoogle Scholar
  77. 77.
    Didier De Bruyn, Dirk Maes, Luigi Mansani, Benoit Giraud, From MYRRHA to XT-ADS: the design evolution of an experimental ADS system, AccApp’07, Pocatello, Idaho, July 29–August 2, 2007Google Scholar
  78. 78.
    L. Cinotti, G. Locatelli, H. Aït Abderrahim, S. Monti, G. Benamati, K. Tucek, D. Struwe, A. Orden, G. Corsini, D. Le Carpentier, The ELSY Project, Paper 377, in Proceedings of the International Conference on the Physics of Reactors (PHYSOR), Interlaken, Switzerland, 14–19 September, 2008Google Scholar
  79. 79.
    Alemberti et al., The European Lead Fast Reactor: Design, Safety Approach and Safety Characteristics, IAEA Technical Meeting on Impact of Fukushima Event on Current and Future FR Designs, Dresden, Germany, 2012Google Scholar
  80. 80.
    Alemberti et al., The Lead Fast Reactor? Demonstrator (ALFRED) and ELFR Design, in International Conference on Fast Reactor and Nuclear Fuel Cycle (FR13), Paris, France, 2013Google Scholar
  81. 81.
    M. Takahashi, LFR Development in Japan, 11th LFR Prov. SSC Meeting, Pisa, Italy, 16 April 2012Google Scholar
  82. 82.
    M. Takahashi et al., Pb-Bi-cooled direct contact boiling water small reactor. Prog Nucl Energy 47, 190–201 (2005)CrossRefGoogle Scholar
  83. 83.
    H. Sekimoto, A. Nagata, Fuel cycle for ?CANDLE? Reactors, in Proc. of Workshop on Advanced Reactors with Innovative Fuels ARWIF-2008, Tsuruga/Fukui, 20–22 February 2008Google Scholar
  84. 84.
    W.J. Kim et al., Supercritical Carbon Dioxide Brayton Power Conversion Cycle Design for Optimized Battery-Type Integral Reactor System, Paper 6142, ICAPP-06, Reno, NV, USA, June 4–8, 2006Google Scholar
  85. 85.
    I.S. Hwang, A sustainable regional waste transmutation system: PEACER, plenary invited paper, ICAPP-06, Reno, NV, U.S.A., June 4–6, 2006Google Scholar
  86. 86.
    C. Smith, W. Halsey, N. Brown, J. Sienicki, A. Moisseytsev, D. Wade, SSTAR: The US lead-cooled fast reactor (LFR). J. Nucl. Mater. 376(3), 255–259 (2008)CrossRefGoogle Scholar
  87. 87.
    M.P. Short, R.G. Ballinger, Design of a Functionally Graded Composite for Service in High Temperature Lead and Lead-Bismuth Cooled Nuclear Reactors, MIT-ANP-TR-131 (2010)Google Scholar
  88. 88.
    GIF-LFR Provisional System Steering Committee (PSSC), Draft System Research Plan for the Lead-cooled Fast Reactor (LFR) (2008)Google Scholar
  89. 89.
    G.I. Toshinsky, O.G. Komlev, I.V. Tormyshev, et al. Effect of Potential Energy Stored in Reactor Facility Coolant on NPP Safety and Economic Parameters, in Proceedings of ICAPP 2011, Nice, France, May 2–5, 2011, Paper 11465Google Scholar

Copyright information

© Springer International Publishing AG, part of Springer Nature 2019

Authors and Affiliations

  • Bahman Zohuri
    • 1
  • Patrick McDaniel
    • 2
  1. 1.Department of Electrical and Computer Engineering, Galaxy Advanced Engineering, Inc.University of New MexicoAlbuquerqueUSA
  2. 2.Department of Chemical and Nuclear EngineeringUniversity of New MexicoAlbuquerqueUSA

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