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Boiling water reactors
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1
Review of environmental effects on fatigue crack growth of austenitic stainless steels /
by
Shack, W. J.
Published 1994
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Government Document
Microform
Book
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2
Irradiation-assisted stress corrosion cracking of model austenitic stainless steel alloys /
Published 2000
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3
Crack growth rates of irradiated austenitic stainless steel weld heat affected zone in BWR environments /
Published 2006
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Government Document
Book
4
Irradiation-assisted stress corrosion cracking of austenitic stainless steels and alloy 690 from Halden phase-II irradiations /
by
Chen, Y.
Published 2008
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Book
5
Radiographic techniques for inspecting experimental boiling water reactor fuel elements /
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McGonnagle, W.J
Published 1958
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6
Theoretical feedback analysis in boiling water reactors /
by
Akcasu, Ziyaeddin A.
Published 1960
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Argonne National Laboratory
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology
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Akcasu, Ziyaeddin A.
1 results
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Chen, Y.
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Chopra, O. K.
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Chung, H. M.
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Gonzales, P.R
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Kassner, T. F.
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McGonnagle, W.J
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Shack, W. J.
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U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation
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U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
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