Suggested Topics within your search.
Showing 1 - 20 results of 21 for search '', query time: 0.19s Refine Results
1
Fatigue strength of smooth and notched specimens of ASME SA 106-B steel in PWR environments /
by Terrell, J. B.
Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988

Government Document Book
2
Effects of temperature on fatigue crack growth of a 508-2 steel in LWR environment /
by Cullen, W. H., Torronen, Kari, Kemppainen, M.
Washington, D.C. : U.S. Nuclear Regulatory Commission, 1983

Government Document Book
4
The Effects of sulfur chemistry and flow rate on fatigue crack growth rates in LWR environments /
Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1985

Government Document Book
5
Proceedings of the Second CSNI Workshop on Ductile Fracture Test Methods : held at Paris, France, April 17-19, 1985 /
[Washington, D.C.] : The Commission, 1988

Government Document Conference Proceeding Book
6
Fatigue strength of ASME SA 106-B welded steel pipes in 288C̊ air environments /
by Terrell, J. B.
Washington, D.C. : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988

Government Document Book
7
Surface spectroscopy of pressure vessel steel fatigue fracture surface films formed in PWR environments /
by Hanninen, H. E.
Washington, D.C. : The Commission, 1987

Government Document Book
8
The Temperature dependence of fatigue crack growth rates of A 351 CF8A cast stainlss steel in LWR environment /
by Cullen, W. H., Taylor, R. E., Törrönen, Kari, 1945-, Kemppainen, M.
Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1984

Government Document Book
9
Structural integrity of water reactor pressure boundary components /
by Loss, F. J.
Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1983

Government Document Book
10
Fatigue crack growth rates of low-carbon and stainless piping steels in PWR environment /
by Cullen, W. H.
Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1985

Government Document Book
11
Size effects on J-R curves for a 302-B plate /
by Hiser, A. L.
Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989

Government Document Book
12
Fatigue crack growth rates of A 508-2 steel in pressurized, high temperature water /
by Cullen, W. H.
Washington, D.C. : The Commission, 1983

Government Document Book
13
Proceedings of the Second CSNI Workshop on Ductile Fracture Test Methods : held at Paris, France, April 17-19, 1985 /
[Washington, D.C.] : The Commission, 1988

This item is not available through EZBorrow. Please contact your institution’s interlibrary loan office for further assistance.
Government Document Conference Proceeding Book
14
Fatigue strength of smooth and notched specimens of ASME SA 106-B steel in PWR environments /
by Terrell, J. B.
Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988

Book
15
Size effects on J-R curves for a 302-B plate /
by Hiser, A. L.
Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989

Book
16
Proceedings of the Third International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth : held at Moscow, USSR May 14-17, 1990 /
[Washington, D.C.] : Springfield, VA : [U.S. Nuclear Regulatory Commission] : Available from Supt. of Docs., U.S. G.P.O. National Technical Information Service, 1990

Conference Proceeding Book
17
Fatigue strength of ASME SA 106-B welded steel pipes in 288C̊ air environments
by Terrell, J. B.
Washington, D.C. : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988

Book
18
The effects of variable amplitude loading on a 533-B steel in high -temperature air and reactor water environments /
by Cullen, W. H.
Washington, D.C. : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989

Book
19
Proceedings of the second International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth : held at Sendai, Japan, May 15-17, 1985 /
Lanham, MD : Materials Engineering Associates : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission, 1986

Conference Proceeding Book
20
Structural integrity of water reactor pressure boundary components : annual report for 1985 /
Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1983

Book
Search Tools: Get RSS Feed — Email this Search — Save Search