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Nuclear power plants > Piping
Subject: Is
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Cracking

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Online Results (10)
1.
Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5
Author
Oussoren, Andrew
Published
Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2017.
Online
https://purl.fdlp.gov/GPO/gpo90001
Location
Yale Internet Resource >> None
Format
Books / Online
2.
Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5
Author
Oussoren, Andrew
Published
Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2017.
Online
https://purl.fdlp.gov/GPO/gpo90002
Location
Yale Internet Resource
Format
Books / Online
3.
Results of open testing for the program to assess the reliability of emerging nondestructive techniques
Author
Meyer, R. M.
Published
Washington, DC : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, August 2017.
Online
https://purl.fdlp.gov/GPO/gpo90006
Location
Yale Internet Resource >> None
Format
Books / Online
4.
Evaluations of structural failure probabilities and candidate inservice inspection programs
Author
Khaleel, M. A.
Published
[Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2009.
Online
http://purl.access.gpo.gov/GPO/LPS117634
Location
Yale Internet Resource >> None
Format
Books / Online
5.
Resolution of Generic Safety Issue 188 steam generator tube leaks or ruptures concurrent with containment bypass from main steam line or feedwater line breaches
Author
Reichelt, E.
Published
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2009.
Online
http://purl.access.gpo.gov/GPO/LPS116738
Location
Yale Internet Resource >> None
Format
Books / Online
6.
Assessment of crack detection in heavy-walled cast stainless steel piping welds using advanced low-frequency ultrasonic methods
Published
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2007.
Online
http://purl.access.gpo.gov/GPO/LPS106114
Location
Yale Internet Resource >> None
Format
Books / Online
7.
Assessment of eddy current testing for the detection of cracks in cast stainless steel reactor piping components
Published
Washington, DC : Division of Fuel, Engineering, and Radiological Research, Division of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2007.
Online
http://purl.access.gpo.gov/GPO/LPS106400
Location
Yale Internet Resource >> None
Format
Books / Online
8.
Fatigue crack flaw tolerance in nuclear power plant piping a basis for improvements to ASME code section XI Appendix L
Published
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Fuel, Engineering and Radiological Research, [2007]
Online
http://purl.access.gpo.gov/GPO/LPS102658
Location
Yale Internet Resource >> None
Format
Books / Online
9.
Non-destructive and failure evaluation of tubing from a retired steam generator
Published
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2007.
Online
http://purl.access.gpo.gov/GPO/LPS106106
Location
Yale Internet Resource >> None
Format
Books / Online
10.
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
11.
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
12.
Pressure and leak-rate tests and models for predicting failure of flawed steam generator tubes
Author
Majumdar, S. (Saurindranath)
Published
Washington, DC : U.S. Nuclear Regulatory Commission : [Supt. of Docs., U.S. G.P.O., distributor, 2000]
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6664
Format
Books / Microforms
13.
Estimating probable flaw distributions in PWR steam generator tubes
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], 1998.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6521
Format
Books / Microforms
14.
Deterministic and probabilistic evaluations for uncertainty in pipe fracture parameters in leak-before-break and in-service flaw evaluations
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 88:25/6443
Format
Books / Microforms
15.
Development of a J-estimation scheme for internal circumferential and axial surface cracks in elbows
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 88:25/6445
Format
Books / Microforms
16.
Fracture behavior of short circumferentially surface-cracked pipe
Published
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, U.S. Nuclear Regulatory Commission Supt. of Docs., U.S. G.P.O. [distributor] ; Springfield, VA : National Technical Information Service [distributor], 1995.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6265
Format
Books / Microforms
17.
Analysis of crack initiation and growth in the high level vibration test at Tadotsu
Published
Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1993.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6078
Format
Books / Microforms
18.
Evaluation and refinement of leak-rate estimation models
Published
Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1991.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/5128
Format
Books / Microforms
19.
Short cracks in piping and piping welds
Published
Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1991-
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/4599/V.1,NO.1-
Format
Books / Microforms
20.
Proceedings of the Seminar on Leak-Before-Break : further developments in regulatory policies and supporting research : held at Taipei, Taiwan, May 11-12, 1989
Author
Seminar on Leak-Before-Break (4th : 1989 : Taipei, Taiwan)
Published
Washington, D.C. : The Office : Available from Supt. of Docs., U.S. G.P.O. ; Springfield, VA : National Technical Information Service, 1990.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:27/0109
Format
Books / Microforms
21.
Slow strain rate testing of a cyclically stabilized A 516 Gr. 70 piping steel in PWR conditions
Author
Hanninen, H. E.
Published
Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/5327
Format
Books / Microforms
22.
Proceedings of the Seminar on Leak-Before-Break : progress in regulatory policies and supporting research : held at Tokyo, Japan, May 14-15, 1987
Author
Seminar on Leak-Before-Break (3rd : 1987 : Tokyo, Japan)
Published
Washington, D.C. : The Office, 1988.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:27/0092
Format
Books / Microforms