Zobrazeno 1 - 10
of 118
pro vyhledávání: '"W.J. Shack"'
Fracture-mechanics crack growth tests were conducted on 25.4-mm-thick compact tension specimens of Types 304L and 316L Stainless steel and Incoloy 825 at 93{degrees}C and 1 atmosphere of pressure in simulated J-13 well water, which is representative
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https://explore.openaire.eu/search/publication?articleId=doi_________::92cb7dfa8f4db44434b4e3b8f7f07949
https://doi.org/10.1520/stp24883s
https://doi.org/10.1520/stp24883s
Autor:
W.J. Shack, O.K. Chopra
The ASME Boiler and Pressure Vessel Code provides 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. While effects
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https://explore.openaire.eu/search/publication?articleId=doi_________::7d004eaf922003ea47451cb8ca6be1f3
https://doi.org/10.2172/573404
https://doi.org/10.2172/573404
In about 1990, the Nuclear Management and Resources Council (NUMARC) submitted for NRC review ten industry reports (IRs) addressing aging issues associated with specific structures and components of nuclear power plants ad one IR addressing the scree
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https://explore.openaire.eu/search/publication?articleId=doi_________::ce60b9a3f1bca5000e41f1813df6263a
https://doi.org/10.2172/392805
https://doi.org/10.2172/392805
Autor:
O.K. Chopra, W.J. Shack
A procedure and correlations are presented for predicting mechanical properties of cast stainless steels in service at temperatures
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f2a8daed2bc67f4d8aa7d8a66666db3c
https://doi.org/10.2172/71383
https://doi.org/10.2172/71383
Autor:
W.F. Michaud, H.M. Chung, T.F. Kassner, W. K. Soppet, J.E. Sanecki, O.K. Chopra, W.E. Ruther, W.J. Shack, R.A. Erck
This report summarizes work performed by Argonne National Laboratory (ANL) on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) during the six months from October 1993 to March 1994. EAC and fatigue of piping, pressur
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https://explore.openaire.eu/search/publication?articleId=doi_________::e2a166baa00a165cca7598e7c2605661
https://doi.org/10.2172/45615
https://doi.org/10.2172/45615
Autor:
O.K. Chopra, W.J. Shack
SME Boiler and Pressure Vessel Code provides construction of nuclear power plant components. Figure I-90 Appendix I to Section III of the Code specifies fatigue design curves for structural materials. While effects of environments are not explicitly
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c3ddb55fd0a24659e4551ab2eae4dd8a
https://doi.org/10.2172/108192
https://doi.org/10.2172/108192
Two advanced light water reactor (LWR) concepts, namely the General Electric Simplified Boiling Water Reactor (SBWR) and the Westinghouse Advanced Passive 600 MWe Reactor (AP600), were reviewed in detail by Argonne National Laboratory. The objectives
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::238680f63277c844c1f5e34b4f208373
https://doi.org/10.2172/10159721
https://doi.org/10.2172/10159721