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Thermal Expansion 6 pp 1–17Cite as

Reactor Core Materials for Advanced High-Temperature Reactor Systems

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Abstract

The advantage of the gas cooled high-temperature reactor (HTR) lies in its development potential for both the direct cycle gas turbine application and the generation of nuclear process heat at core gas outlet temperatures between 850° and 1000°C maximum. The change over from the steam cycle HTR, having a maximum core outlet temperature of 750°C, to the direct cycle or the nuclear process heat HTRs, having these higher gas temperatures, presents a considerable challenge to the material technology involved. In this paper, problems arising in these new reactor applications and the present state of the art concerning the core-specific components are described. This group includes coated fuel particles, fuel elements for the different HTR-types (spherical elements and block-type elements), and the reflector.

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References

  1. G. Dietrich, H.G. Eickhoff, F. Niehaus, H.F. Niessen: Nucl. Eng. Des. 34, 1975, 3–13

    Article  Google Scholar 

  2. V. Maly, R. Schulten, E. Teuchert: Atomwirtschaft 19, 1974, 601–603

    CAS  Google Scholar 

  3. W. Cautius, J. Engelhard, G. Ivens: Atomwirtschaft 19, 1974, 444–450

    CAS  Google Scholar 

  4. H. Nickel: High Temp. — High Press. 8 (1976) 123–141, and

    CAS  Google Scholar 

  5. H. Nickel:Proc. ANS-Conference on World Nuclear Power, Washington D.C. 1976, Transactions Vol. 24 (1976) 160

    Google Scholar 

  6. T.G. Gulden, J.L. Scott, C. Moreau: Proc. ANS Conference on Gas-Cooled Reactors, Gatlinburg, Tenn., 1974, Conf. 740501, 176–182

    Google Scholar 

  7. H. Nickel, E. Baithesen: Kerntechnik 17 (1975) 205–214

    CAS  Google Scholar 

  8. D.P. Harmon, C.B. Scott: J. Nucl. Techn. 1977 (in press)

    Google Scholar 

  9. J.C. Bokros, K. Koyama: J. App. Phys. 41 (1970) 2146–2155

    Article  CAS  Google Scholar 

  10. R. Förthmann, E. Groos, H. Grübmeier: KFA-Report Jül-1226 (1975) 1–29

    Google Scholar 

  11. A. Naoumidis: J. Nucl. Mat. 48 (1973) 118–124

    Article  CAS  Google Scholar 

  12. G.B. Engle, M.R. Everett, W.P. Eatherly: Proc. ANS-Conference on Gas-Cooled Reactors, Gatlinburg (Tenn.), 1974), Conf. 740501, 288–305

    Google Scholar 

  13. D.L. Leushacke, H. Cords3 J. Semmler, E. Spann: Proc. IAEA Symp. on Gas-Cooled Reactors with Emphasis on Advanced Systems, Jülich/FRG, 1976, paper SM-200/33, Vol. I, 291–307

    Google Scholar 

  14. F.M. Collins: Proc. 1st Carbon Conf., pp. 177–187 (1956) Pergamon Press

    Google Scholar 

  15. J. Fourré, A. Pernollet, W. Delle, G. Haag: Preprints Int. Carbon Conf. CARBON ’76, Baden-Baden, pp. 353–356 (1976)

    Google Scholar 

  16. J. Okada: Proc. 4th Carbon Conf., pp. 547–552 (1959) Pergamon Press

    Google Scholar 

  17. W. Delle: Preprints Int. Carbon Conf. CARBON ’72, Baden-Baden, pp. 176–178 (1972)

    Google Scholar 

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Author information

Authors and Affiliations

  1. Institut für Reaktorwerkstoffe, Kernforschungsanlage Jülich GmbH, Germany

    H. Nickel

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  1. H. Nickel
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Editor information

Editors and Affiliations

  1. Atomic Energy of Canada, Ltd., Pinawa, Manitoba, Canada

    Ian D. Peggs

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© 1978 Purdue Research Foundation

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Nickel, H. (1978). Reactor Core Materials for Advanced High-Temperature Reactor Systems. In: Peggs, I.D. (eds) Thermal Expansion 6. Springer, Boston, MA. https://doi.org/10.1007/978-1-4615-9086-6_1

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  • DOI: https://doi.org/10.1007/978-1-4615-9086-6_1

  • Publisher Name: Springer, Boston, MA

  • Print ISBN: 978-1-4615-9088-0

  • Online ISBN: 978-1-4615-9086-6

  • eBook Packages: Springer Book Archive

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