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Microstructural examination of low activation ferritic steels following irradiation in ORR at 330 and 400 °C to ∼10 dpa

  • Published:2004-08 Issue: Volume:329-333 Page:304-308
  • ISSN:0022-3115
  • Container-title:Journal of Nuclear Materials
  • language:en
  • Short-container-title:Journal of Nuclear Materials

Author:

Gelles D.S

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference10 articles.

1. Tensile response of low activation ferritic steels irradiated in ORR at temperatures in the range 60–400 °C

2. R.M. Ermi, M.L. Hamilton, D.S. Gelles and A.M. Ermi, DOE/ER-0313/29 (2000) 103

3. D.S. Gelles and M.L. Hamilton, DOE/ER-0045/13 (1985) 128

4. D.S. Gelles and M.L. Hamilton, DOE/ER-0045/16 (1986) 131

5. D.S. Gelles, in: R.L. Klueh, D.S. Gelles, M. Okada, N.H. Packan, (Eds.), Reduced Activation Materials for Fusion Reactors ASTM STP 1047, ASTM, Philadelphia, PA, 1990, p. 113

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