Irradiation-assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor
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Irradiation-assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor by H. M. Chung

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Published by Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Supt. of Docs., U.S. G.P.O. [distributor] in Washington, DC .
Written in English

Subjects:

  • Boiling water reactors.,
  • Nuclear reactors -- Materials -- Stress corrosion.,
  • Nuclear reactors -- Materials -- Effect of radiation on.

Book details:

Edition Notes

Other titlesIrradiation assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor.
Statementprepared by H.M. Chung, W.R. Ruther, R.V. Strain.
ContributionsRuther, W. R., Strain, R. V., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., Argonne National Laboratory.
The Physical Object
FormatMicroform
Paginationx, 30 p.
Number of Pages30
ID Numbers
Open LibraryOL15546523M

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