Selection of Suitable Metallic Materials for Nuclear Power Reactors



The selection of suitable metallic materials for engineering purposes is based primarily on the fundamental physical properties of potential base metals and constituents of alloys under the anticipated service conditions. The main physical properties are:
  • crystal structure,

  • phase transformation,

  • density,

  • melting point,

  • boiling point,

  • vapour pressure,

  • diffusivity and permeability,

  • specific heat,

  • thermal expansion,

  • thermal conductivity.


Power Reactor Austenitic Steel Ferritic Steel Nickel Base Alloy Fast Breeder Reactor 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.


Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.


  1. 1.
    R.C.Weast. Handbook of Chemistry and Physics, CRC-Press Cleveland (Ohio) 55th Edition, 1974–1975.Google Scholar
  2. 2.
    D’Ans-Lax. Taschenbuch für Chemiker und Physiker, Springer-Verlag Berlin, 3. Aufl., Bd. 1, 1967.Google Scholar
  3. 3.
    Landolt-Börnstein. Zahlenwerte und Funktionen aus Naturwissen- schaften und Technik, Springer-Verlag Berlin, 6. Aufl.Google Scholar
  4. 4.
    K.Lintner and E.Schmid. Werkstoffe des Reaktorbaues, Springer-Verlag Berlin 1962.Google Scholar
  5. 5.
    E.Hillner. Corrosion of Zierconium Base Alloys–An Overview, Proc. 3rd Intern. Conf. “Zirconium in the Nuclear Industry” Quebec, Canada, August 1976. ASTM Spec. Techn. Publ. 633 (1977) 211–235.Google Scholar
  6. 6.
    Broschüre Material “Zirkonium” VDM-Zirkonium-Gesellschaft Duisburg.Google Scholar
  7. 7.
    H.-H.Piehl. Werkstofftechnik in Kernkraftwerken–Erfahrung und Entwicklung aus der Sicht des Werkstoffherstellers, Thyssen Techn. Ber. 2 (1978) 19–25.Google Scholar
  8. 8.
    H.Böhm. Hüllwerkstoffe für Brennelemente schneller Reaktoren, Atomkernenergie 15 (1970) 14–18.Google Scholar
  9. 9.
    K.Ehrlick. Werkstoffe für Fusionsreaktoren, KfK 2590 (1978).Google Scholar
  10. 10.
    W.Dienst. Hochtemperatur-Werkstoffe. Werkstofftechn. Verlagsges. Karlsruhe 1978.Google Scholar
  11. 11.
    D.R.Harries. Neutron Irradiation Embrittlement of Austenitic Stainless Steels and Nickel Base Alloys, J. BNES 5 (1966) 74–87.Google Scholar
  12. 12.
    R.H.Sterne, Jr. and L.E.Steele. Steels for Commercial Nuclear Power Reactor Pressure Vessels, Nucl. Eng. Design 10 (1969) 259–307.CrossRefGoogle Scholar
  13. 13.
    O.Kubaschewski and E.L.Evans. Metall. Thermochemistry, London (1956) 331–338.Google Scholar
  14. 14.
    H.Michaelis. Kernenergie, dtv-Deutscher Taschenbuch Verlag, Wissenschaftliche Reihe 4137 (1977).Google Scholar
  15. 15.
    A.Klusmann and H.Völcker. Brennelemente von Kernreaktoren, Thiemig Verlag, München 1969.Google Scholar
  16. 16.
    R.Darras and H.Loriers. Problmes de corrosion des aciers ordinaires ou alliés par le gaz carbonique aux temperatures élevées, Bull. Inf. Sc. Techn. CEA 104 (1966) 1–7.Google Scholar
  17. 17.
    O.Kimball. Structural Materials Application and Requirements for Nuclear Process Gas Cooled Reactor Systems, 16th INCO Power Conference, Wrightsville Beach, N.C., USA, August 1978.Google Scholar
  18. 18.
    W.Theymann, J.Jauer. Evaluation of Materials for HTR-Components, INCO Power Conference, Lausanne, Switzerland, Oct.5–7, 1977 Paper 3.Google Scholar
  19. 19.
    R.A.U.Huddle. The Surface Reactions of HTR Helium with Turbine Materials and their Influence on Creep Behaviour, CEGB-Conf “Deposition and Corrosion in Gas Turbines”, Sudbury HOuse, Dec. 1972.Google Scholar
  20. 20.
    S.Leistikow, R.Kraft and E.Pott. Comparative Studies of High-Temperature Oxidation of Four Austenitic CrNi-steels in Helium with Water Vapor and Hydrogen Additions, Proc. Conf. “Material and Coatings to Resist High-Temperature Oxidation and Corrosion” Düsseldorf, Mai 1977, 21–38.Google Scholar
  21. 21.
    J.Weber. Werkstoffverhalten in Kernkraftwerken, unter besonderer Berücksichtigung der Leichtwasserreaktoren, Techn. Rundschau SULZER, Sonderheft “NUCLEX 75” s. 19–30 (1975).Google Scholar
  22. 22.
    M.A.Cordovi. Existing and Potential Applications for Alloy 800. Proc. Intern. Conf. “Alloy 800”, Petten, The Netherlands, March 1978, 3–21.Google Scholar
  23. 23.
    M.A.Cordovi. Corrosion Considerations in Light Water-Cooled Nuclear Power Plants, INCO Power Conference Kyoto, Japan, 1972.Google Scholar
  24. 24.
    J.E.Draley et al. Corrosion in Aqueous Systems, 3rd UN-Conf. on Peaceful Uses of Atomic Energy, May 1964, A/CONF. 28/P/243.Google Scholar
  25. 25.
    K.Videm. Mild Steel in Primary Circuits of Water Cooled Power Reactors, 3rd UN-Conf. on Peaceful Uses of Atomic Energy, May 1964, A/CONF. 28/P/592.Google Scholar
  26. 26.
    G.Grützner and H.Jesper. Blech 11 (1964) 503/514 and 590/597.Google Scholar
  27. 27.
    H.U.Borgstedt. Corrosion and Mass Transfer in Sodium-Cooled Fast Reactors, Rev. Coat. Corr. 2, 1977 (121–141)Google Scholar
  28. H.U.Borgstedt. Korrosion in Alkalimetallkreisläufen, I. Mechanismen and Phänomene, Werkst. Korr. 26 (1975) 103–114.CrossRefGoogle Scholar
  29. 28.
    D.R.Harries, I.E.Antill. Core Component and Circuit Materials for Sodium-Cooled Fast Reactors, INCO Power Conference Lausanne, Switzerland, Oct. 5–7, 1977, Paper 2.Google Scholar
  30. 29.
    M.Weisz. Incidence des Phénomènes Specifiquement Nucléaires sur le Choix des Matériaux Métalliques, Revue Générale Nucleaire (1977) 283–291.Google Scholar
  31. 30.
    K.Ehrlich and W.Dietz. Stand und Tendenzen in der Entwicklung von Hüll-und Kernstrukturwerkstoffen, Atoomenergie 18 (1976) 189–194.Google Scholar
  32. 31.
    W.Dienst et al. Mechanische und chemische Wechselwirkung zwischen Brennstoff und Hüllrohr in Schnellbrüterstäben, KfK-Nachr. 10, 3–4 (1978) 18–22.Google Scholar
  33. 32.
    P.Patriarca. Private comm. ORNL (1974).Google Scholar
  34. 33.
    J.C.Griess, J.H.DeVan and W.A.Maxwell. Effect of a High Heat Flux on the Corrosion of 2 4 Cr 1 Mo-Steel in Superheated Steam. Mater. Perform. 17 (1978) 9–15.Google Scholar

Copyright information

© Plenum Press, New York 1980

Authors and Affiliations

  1. 1.Institute for Material and Solid State ResearchNuclear Research Center KarlsruheFederal Republic of Germany

Personalised recommendations