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Author/Creator: Is
Is Is Not
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology
Language: Is
Is Is Not
English
Subject: Is
Is Is Not
Fatigue

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Current results range from 1984 to 2005

1.
Effect of material heat treatment on fatigue crack initiation in austenitic stainless steels in LWR environments
Author
Chopra, O. K.
Published
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, [2005]
Online
http://purl.access.gpo.gov/GPO/LPS100031
Location
Yale Internet Resource >> None
Format
Books / Online
2.
Review of the margins for ASME code fatigue design curve effects of surface roughness and material variability
Author
Chopra, O. K.
Published
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2003.
Online
http://purl.access.gpo.gov/GPO/LPS99657
Location
Yale Internet Resource >> None
Format
Books / Online
3.
Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments
Author
Chopra, O. K.
Published
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 2002.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6787
Format
Books / Microforms
4.
Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments
Author
Chopra, O. K.
Published
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2002.
Online
http://purl.access.gpo.gov/GPO/LPS99582
Location
Yale Internet Resource >> None
Format
Books / Online
5.
Environmental effects on fatigue crack initiation in piping and pressure vessel steels
Author
Chopra, O. K.
Published
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6717
Format
Books / Microforms
6.
Environmental effects on fatigue crack initiation in piping and pressure vessel steels
Author
Chopra, O. K.
Published
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.
Online
http://purl.access.gpo.gov/GPO/LPS99324
Location
Yale Internet Resource >> None
Format
Books / Online
7.
Evaluation of WF-70 weld metal from the Midland Unit 1 reactor vessel
Published
Washington, DC : The Office : [Supt. of Docs., U.S. G.P.O., distributor], 2000.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/5736
Format
Books / Microforms
8.
Pretest analysis of a 1:4-scale prestressed concrete containment vessel model
Published
Washington, DC : The Office : [Supt. of Docs., U.S. G.P.O., distributor], 2000.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6685
Format
Books / Microforms
9.
Effects of LWR coolant environments on fatigue design curves of austenitic stainless steels
Author
Chopra, O. K.
Published
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1999.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/5704
Format
Books / Microforms
10.
Effects of LWR coolant environments on fatigue design curves of austenitic stainless steels
Author
Chopra, O. K.
Published
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.
Online
http://purl.access.gpo.gov/GPO/LPS99071
Location
Yale Internet Resource >> None
Format
Books / Online
11.
Corrosion fatigue of alloys 600 and 690 in simulated LWR environments
Author
Ruther, W. E.
Published
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1996.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6383
Format
Books / Microforms
12.
Stainless steel round robin test : centrifugally cast stainless steel screening phase
Published
Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/4970
Format
Books / Microforms
13.
Structural integrity of water reactor pressure boundary components
Published
Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1983-
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/3228/v.1-
Format
Books / Microforms