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Nuclear power plants > Piping

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Online Results (88)
1.
Flow-induced vibration handbook for nuclear and process equipment
Published
Hoboken, NJ : John Wiley & Sons, Inc., [2022]
Online
Online book
Location
Yale Internet Resource >> None
Format
Books / Online
2.
Effects of thermal aging on fracture toughness and charpy-impact strength of stainless steel pipe welds
Author
Chopra, O. K.
Published
Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, August 2018.
Online
https://purl.fdlp.gov/GPO/gpo152202
Location
Yale Internet Resource >> None
Format
Books / Online
3.
Simulation of the G3.1 Experiment at PKL Facility Using RELAP5/Mod3.3
Author
Villanueva, J. F.
Published
Washington, DC : Division of System Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, November 2018.
Online
https://purl.fdlp.gov/GPO/gpo186915
Location
Yale Internet Resource >> None
Format
Books / Online
4.
Simulation of the G3.1 Experiment at PKL Facility Using RELAP5/Mod3.3
Author
Villanueva, J. F.
Published
Washington, DC : Division of System Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, November 2018.
Online
https://purl.fdlp.gov/GPO/gpo186915
Location
Yale Internet Resource
Format
Books / Online
5.
Results of blind 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, June 2017.
Online
http://purl.fdlp.gov/GPO/gpo82559
Location
Yale Internet Resource >> None
Format
Books / Online
6.
Steam line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment
Author
Jung, Han-Sik
Published
Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, May 2017.
Online
http://purl.fdlp.gov/GPO/gpo82529
Location
Yale Internet Resource >> None
Format
Books / Online
7.
Steam line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment
Author
Jung, Han-Sik
Published
Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, May 2017.
Online
https://purl.fdlp.gov/GPO/gpo82529
Location
Yale Internet Resource
Format
Books / Online
8.
Cladding behavior during postulated loss-of-coolant accidents
Author
Billone, M. C.
Published
Washington, DC : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, July 2016.
Online
http://purl.fdlp.gov/GPO/gpo70902
Location
Yale Internet Resource >> None
Format
Books / Online
9.
Feedwater line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment
Author
Jung, Han-Sik
Published
Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, November 2016.
Online
http://purl.fdlp.gov/GPO/gpo74472
Location
Yale Internet Resource >> None
Format
Books / Online
10.
Feedwater line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment
Author
Jung, Han-Sik
Published
Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, November 2016.
Online
http://purl.fdlp.gov/GPO/gpo74472
Location
Yale Internet Resource
Format
Books / Online
11.
Applying ultrasonic testing in lieu of radiography for volumetric examination of carbon steel piping
Author
Moran, T. L.
Published
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, September 2015.
Online
http://purl.fdlp.gov/GPO/gpo61382
Location
Yale Internet Resource >> None
Format
Books / Online
12.
Guidelines for inservice testing at nuclear power plants : inservice testing of pumps and valves and inservice examination and testing of dynamic restraints (snubbers) at nuclear power plants, final report
Author
Bedi, Gurjendra S.
Published
Washington, DC : Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, October 2013.
Online
http://purl.fdlp.gov/GPO/gpo70684
Location
Yale Internet Resource >> None
Format
Books / Online
13.
The technical basis supporting ASME code, section XI, appendix VIII : performance demonstration for ultrasonic examination
Author
Doctor, S. R.
Published
Washington, DC : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2013.
Online
http://purl.fdlp.gov/GPO/gpo38059
Location
Yale Internet Resource >> None
Format
Books / Online
14.
Assessment of NDE methods on inspection of HOPE butt fusion piping joints for lack of fusion
Published
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2012]
Online
http://purl.fdlp.gov/GPO/gpo32236
Location
Yale Internet Resource >> None
Format
Books / Online
15.
XLPR pilot study report
Author
Rudland, D. J. (David J.)
Published
Washington, DC : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, May 2012.
Online
http://purl.fdlp.gov/GPO/gpo77163
Location
Yale Internet Resource >> None
Format
Books / Online
16.
An assessment of ultrasonic techniques for far-side examinations of austenitic stainless steel piping welds
Published
Washington, DC : U.S. Nuclear Regulatory Commission, [2011]
Online
http://purl.fdlp.gov/GPO/gpo19165
Location
Yale Internet Resource >> None
Format
Books / Online
17.
Evaluation of JNES equipment fragility tests for use in seismic probability risk assessments for U.S. nuclear power plants
Author
Kennedy, R.
Published
[Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2011]
Online
http://purl.fdlp.gov/GPO/gpo22766
Location
Yale Internet Resource >> None
Format
Books / Online
18.
Guidelines for inservice testing at nuclear power plants inservice testing of pumps and valves and inservice examination and testing of dynamic restraints (snubbers) at nuclear power plants : draft report for comment
Author
Bedi, Gurjendra S.
Published
Washington, D.C. : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, [2011]
Online
http://purl.fdlp.gov/GPO/gpo23465
Location
Yale Internet Resource >> None
Format
Books / Online
19.
Analysis of JNES seismic tests on degraded piping
Published
[Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2010]
Online
http://purl.fdlp.gov/GPO/gpo6506
Location
Yale Internet Resource >> None
Format
Books / Online
20.
Inservice testing of pumps and valves, and inservice examination and testing of dynamic restraints (snubbers) at nuclear power plants draft report for comment
Author
Tingen, S. G.
Published
[Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, [2010]
Online
http://purl.fdlp.gov/GPO/gpo29582
Location
Yale Internet Resource >> None
Format
Books / Online
21.
Steam generator tube integrity issues pressurization rate effects, failure maps, leak rate correlation models, and leak rates in restricted areas
Published
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2009]
Online
http://purl.access.gpo.gov/GPO/LPS119872
Location
Yale Internet Resource >> None
Format
Books / Online
22.
Fabrication flaw density and distribution in repairs to reactor pressure vessel and piping welds
Author
Schuster, G. J.
Published
Washington, D.C. : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2008]
Online
http://purl.access.gpo.gov/GPO/LPS98398
Location
Yale Internet Resource >> None
Format
Books / Online
23.
Field evaluation of low-frequency SAFT-UT on coast stainless steel and dissimilar metal weld components
Author
Diaz, Aaron A.
Published
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2008.
Online
http://purl.access.gpo.gov/GPO/LPS108577
Location
Yale Internet Resource >> None
Format
Books / Online
24.
Proceedings of the Tenth NRC/ASME Symposium on Valves, Pumps and Inservice Testing held at L'Enfant Plaza Hotel Washington, DC, July 14-16, 2008
Author
NRC/ASME Symposium on Valve and Pump Testing
Published
Washington, DC : Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission ; New York, N.Y. : Board on Nuclear Codes and Standards of the American Society of Mechanical Engineers, [2008]
Online
http://purl.access.gpo.gov/GPO/LPS120709
Location
Yale Internet Resource >> None
Format
Books / Online
25.
Seismic analysis of large-scale piping systems for the JNES-NUPEC ultimate strength piping test program
Author
DeGrassi, G.
Published
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2008.
Online
http://purl.access.gpo.gov/GPO/LPS108567
Location
Yale Internet Resource >> None
Format
Books / Online