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Developing steels for service in fusion reactors

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Abstract

Steels used in the fusion reactors of the future will be exposed to a high-energy neutron irradiation field at elevated temperatures. To reduce the production of long-lived radioactive isotopes and deleterious mechanical effects, steels are being developed in which certain common alloying elements are eliminated. Several such new ferritic/martensitic steels show excellent properties in the unirradiated condition as well as after neutron irradiation in a fast-fission reactor.

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References

  1. S.N. Rosenwasser et al., “The Application of Martensitic Stainless Steels in Long Lifetime Fusion First Wall/ Blankets,” J. Nuct Mater., 85 & 86 (1979), pp. 177–182.

    Google Scholar 

  2. D.S. Gelles and M.L. Hamilton, “Effects of Irradiation on Low Activation Ferritic Alloys,” J. Nucl. Mater., 148 (1987), pp. 272–278.

    CAS  Google Scholar 

  3. D. Dulieu, K.W. Tupholme, and G.J. Butterworth, “Development of Low-Activation Martensitic Stainless Steels,” J. Nucl. Mater., 141-143 (1986), pp. 1097–1101.

    CAS  Google Scholar 

  4. M. Tamura et al., “Development of Potential Low Activation Ferritic and Austenitic Steels,” J. Nucl. Mater., 141-143 (1986), pp. 1067–1073.

    CAS  Google Scholar 

  5. R.L. Klueh and E.E. Bloom, “The Development of Ferritic Steels for Fast Induced-Radioactivity Decay for Fusion Reactor Applications,” Nucl. Eng. Design/Fusion, 2 (1985), pp. 383–389

    CAS  Google Scholar 

  6. R.L. Klueh and P.J. Maziasz, “Microstructure of Citromium-Tungsten Steels,” Met. Trans., 20A (1989), pp, 373–382.

    CAS  Google Scholar 

  7. R.L. Klueh, “Heat Treatment Behavior and Tensile Properties of Cr-W Steels,” Met. Trans., 20A (1989), pp. 463–470.

    CAS  Google Scholar 

  8. R.L. Klueh and W.R. Corwin, “Impact Behavior of Cr-W Steels,” J. Materials Eng., 11 (1989), pp. 169–175.

    CAS  Google Scholar 

  9. R.L. Klueh and D.J. Alexander, “Irradiation Effects on Impact Behavior of 12Cr-1MoVW and 2.25Cr-1Mo Steels,” Effects of Radiation on Materials: Proceedings of the 15th Symposium, STP 1125, ed. R.S. Stoller, A.S. Kumar, and D.S. Gelles (Philadelphia, PA: ASTM, to be published).

  10. R.L. Klueh, “Irradiation Hardening of Ferritic Steels: Effect of Composition,” J. Nucl. Mater., 179-181 (1991), pp. 728–732.

    CAS  Google Scholar 

  11. R.L. Klueh, D.J. Alexander, and P.J. Maziasz, “Impact Behavior of Reduced-Activation Ferritic Steels Irradiated in the Fast Flux Test Facility,” J. Nucl. Mater., 186 (1992), pp. 185–195.

    CAS  Google Scholar 

  12. G.R. Odette, P.M. Lombrozo, and R.A. Wullaert, “Relationship Between Irradiation Hardening and Embrittlement of Pressure Vessel Steels,” Effects of Radiation on Materials: Twelfth International Symposium. STP870, ed. F.A. Garner and J.S. Perin (Philadelphia, PA: ASTM, 1985), pp. 840–860.

    Google Scholar 

  13. R.L. Klueh, “Chromium-Molybdenum Steels for Fusion Reactor First Walls: A Review,” Nucl. Eng. Design, 72 (1981), pp. 329–344.

    Google Scholar 

  14. R.L. Klueh and D.J. Alexander, “Heat-Treatment Effect on Impact Properties of Reduced-Activation Steels,” J. Nucl. Mater., 179-181 (1991), pp, 679–683.

    CAS  Google Scholar 

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Klueh, R.L. Developing steels for service in fusion reactors. JOM 44, 20–24 (1992). https://doi.org/10.1007/BF03222814

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  • DOI: https://doi.org/10.1007/BF03222814

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