Zobrazeno 1 - 10
of 27
pro vyhledávání: '"Hardayal S. Mehta"'
Autor:
Hardayal S. Mehta, Sampath Ranganath
The role of fracture mechanics in ASME Section XI applications comes in the form of evaluation of indications or flaws detected during inservice inspection of nuclear components. The need to include the influence of significant plastic deformation, w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::151b6567e104e686caf964e0e5b31061
https://doi.org/10.1115/1.861981_ch33
https://doi.org/10.1115/1.861981_ch33
Publikováno v:
Volume 1A: Codes and Standards.
The ASME Code fatigue curves (S–N curves) are used in the fatigue evaluation of reactor components. For the assessment of high frequency cyclic loading (such as those produced by flow-induced vibrations), where the number of cycles is expected to b
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6dfdf2120bf453c5af13fc92de15f292
https://doi.org/10.1115/pvp2017-66242
https://doi.org/10.1115/pvp2017-66242
Autor:
Hardayal S. Mehta
Publikováno v:
Global Applications of the ASME Boiler & Pressure Vessel Code
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::34a0b6850c7b5c3df9dc0cbf96e3a837
https://doi.org/10.1115/1.861073_ch16b
https://doi.org/10.1115/1.861073_ch16b
Autor:
Hardayal S. Mehta, Sampath Ranganath
Publikováno v:
Volume 1A: Codes and Standards.
When the ASME Code fatigue curves (S-N curves) are used in the assessment of high frequency cyclic stresses (such as those produced by flow-induced vibrations), the question arises as to the need for an E correction (i.e., multiplying the calculated
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::caea3d67f27508d1eaacd2752d627674
https://doi.org/10.1115/pvp2015-45619
https://doi.org/10.1115/pvp2015-45619
Autor:
Raymond M. Pace, Brian D. Frew, Hardayal S. Mehta, Hal Gustin, Anthony Giannuzzi, Katie E. Woods, Yuting Rui
Publikováno v:
Volume 6B: Materials and Fabrication.
During Refueling Outage 18 (RFO18, April 2011) Pilgrim Nuclear Power Station (PNPS) identified crack-like indications on the Steam Separator Lifting Lugs. A multi-disciplinary engineering effort was undertaken to determine the cause of the cracking a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5b3f198b8b014008959c89195eb634f2
https://doi.org/10.1115/pvp2014-28091
https://doi.org/10.1115/pvp2014-28091
Autor:
Gary L. Stevens, Hardayal S. Mehta, Joshua Kusnick, Mark Kirk, Michael L. Benson, Timothy J. Griesbach, Daniel Sommerville
Publikováno v:
Volume 1: Codes and Standards.
A previous PVP paper [1] identified suggested improvements to be made to ASME Code, Section XI, Nonmandatory Appendix G, “Fracture Toughness Criteria for Protection Against Failure” [2]. That paper also identified that the current version of Appe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::00e5dc1647ccafc25386cfe6b8271571
https://doi.org/10.1115/pvp2014-28397
https://doi.org/10.1115/pvp2014-28397
Publikováno v:
Volume 1: Codes and Standards.
This paper describes the evaluation performed to determine the bounding T-RTNDT for the Boiling Water Reactor (BWR) Water Level Instrumentation (WLI) nozzle for use in establishing reactor pressure vessel Pressure-Temperature (P-T) curves. The evalua
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::12a4bfdafbd01bc450f1be25adc7f896
https://doi.org/10.1115/pvp2012-78734
https://doi.org/10.1115/pvp2012-78734
Publikováno v:
Volume 1: Codes and Standards.
This paper is the second in a continuing series of papers to highlight additional bases and recommended improvements to Appendix G. In 2008, the authors prepared a paper that reviewed some of the original basis documents for Appendix G for calculatin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a5494b44f9220d0261491cf0f500108c
https://doi.org/10.1115/pvp2011-57015
https://doi.org/10.1115/pvp2011-57015
Publikováno v:
ASME 2010 Pressure Vessels and Piping Conference: Volume 1.
NUREG-1801, Rev. 1, Section XI.M.13, states that an ASME Code Section XI VT-3 examination is required to be performed of reactor internal components. In addition, the NUREG report specifies that for the license renewal period, these inspections shall
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1d05c005659fc7486d59c62e2e832ae9
https://doi.org/10.1115/pvp2010-25974
https://doi.org/10.1115/pvp2010-25974
Publikováno v:
Volume 6: Materials and Fabrication, Parts A and B.
Jet pumps in a boiling water reactor (BWR) are located in the annulus region between the core shroud and the reactor vessel wall and provide core flow to control reactor power. Between 16 and 24 jet pumps are included in BWR/3 through BWR/6 plants, d
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4a6505ad9a5b1ea1289908152d4520f7
https://doi.org/10.1115/pvp2009-77131
https://doi.org/10.1115/pvp2009-77131