Zobrazeno 1 - 10
of 48
pro vyhledávání: '"Omesh K. Chopra"'
Publikováno v:
Journal of Pressure Vessel Technology. 139
The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) provides rules for the design of Class 1 components of nuclear power plants. However, the Code design curves do not address the effects of light water reactor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e5a255aea98d20e19a44b1b9daa74173
https://doi.org/10.1115/1.4035885
https://doi.org/10.1115/1.4035885
Autor:
Omesh K. Chopra, A. S. Rao
Publikováno v:
Journal of Pressure Vessel Technology. 138
Cast austenitic stainless steel (CASS) materials, which have a duplex structure consisting of austenite and ferrite phases, are susceptible to thermal embrittlement during reactor service. In addition, the prolonged exposure of these materials, which
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f09f2a275a6fa0b109ad8b4eae226b5d
https://doi.org/10.1115/1.4031909
https://doi.org/10.1115/1.4031909
Autor:
Omesh K. Chopra, A. S. Rao
Publikováno v:
Journal of Nuclear Materials. 412:195-208
Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of light water reactor (LWR) pressure vessels because of their relatively high strength, ductility, and fracture toughness. However, exposure to ne
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::929f06a587494580f759e56f4717f1a6
https://doi.org/10.1016/j.jnucmat.2011.02.059
https://doi.org/10.1016/j.jnucmat.2011.02.059
Autor:
A. S. Rao, Omesh K. Chopra
Publikováno v:
Journal of Nuclear Materials. 409:235-256
Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of light water reactor (LWR) pressure vessels because of their relatively high strength, ductility, and fracture toughness. However, exposure to ne
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2efff6f918870ebd7664c5720c776f1d
https://doi.org/10.1016/j.jnucmat.2010.12.001
https://doi.org/10.1016/j.jnucmat.2010.12.001
Publikováno v:
Journal of Nuclear Materials. 392:243-248
Sodium environmental effects are key limiting factors in the high temperature structural design of advanced sodium-cooled reactors. A guideline is needed to incorporate environmental effects in the ASME design rules to improve the performance reliabi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c64dd571981f4020a8f1c499db06dffa
https://doi.org/10.1016/j.jnucmat.2009.03.039
https://doi.org/10.1016/j.jnucmat.2009.03.039
Autor:
T.Todd Pleune, Omesh K. Chopra
Publikováno v:
Nuclear Engineering and Design. 197:1-12
The ASME Boiler and Pressure Vessel Code contains rules for the construction of nuclear power plant components. Figures I-9.1 through I-9.6 of Appendix I to Section III of the Code specify fatigue design curves for structural materials. However, the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0923016d8a1ff5f4c39aa63eebcffaa4
https://doi.org/10.1016/s0029-5493(99)00252-6
https://doi.org/10.1016/s0029-5493(99)00252-6
Autor:
Pingsha Dong, T.F. Kassner, W. J. Shack, H.M. Chung, Frederick W. Brust, Jinmiao Zhang, Omesh K. Chopra, J. H. Park
Publikováno v:
Nuclear Engineering and Design. 194:205-223
The effect of dissolved oxygen level on fatigue life of austenitic stainless steels is discussed and the results of a detailed study of the effect of the environment on the growth of cracks during fatigue initiation are presented. Initial test result
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::60991538c1b6d3d04fb2407796c6c8ff
https://doi.org/10.1016/s0029-5493(99)00206-x
https://doi.org/10.1016/s0029-5493(99)00206-x
Autor:
W. J. Shack, Omesh K. Chopra
Publikováno v:
Journal of Pressure Vessel Technology. 121:49-60
Recent test data illustrate potentially significant effects of light water reactor (LWR) coolant environments on the fatigue resistance of carbon and low-alloy steels. The crack initiation and crack growth characteristics of carbon and low-alloy stee
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b4eaa0121f2207e464f372b56a3fbef1
https://doi.org/10.1115/1.2883667
https://doi.org/10.1115/1.2883667
Autor:
W. J. Shack, Omesh K. Chopra
Publikováno v:
Nuclear Engineering and Design. 184:49-76
The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Figure I-90 of Appendix I to Section III of the Code specifies fatigue design curves for structural materials. Although effects of reactor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::43ecc5998edab81a34d310a4335bad38
https://doi.org/10.1016/s0029-5493(97)00368-3
https://doi.org/10.1016/s0029-5493(97)00368-3