Zobrazeno 1 - 10 of 143 pro vyhledávání: '"W.L. Server"'
2
Evaluating the fracture toughness of reactor pressure vessel (RPV) materials subject to embrittlement**Some portions of this chapter have been gleaned from Chapter 3 of: International Atomic Energy Agency, Integrity of Reactor Pressure Vessels in Nuclear Power Plants: Assessment of Irradiation Embrittlement Effects in Reactor Pressure Vessel Steels, IAEA Nuclear Energy Series NP-T-3.11, IAEA, Vienna (2009), a chapter authored by the first author of this chapter (no attribution in the IAEA document)Notice: This manuscript has been authored by UT-Battelle, LLC, under Contract No. DE-AC05-00OR22725 with the US Department of Energy. The United States Government retains and the publisher by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes
Autor: Mikhail A. Sokolov, W.L. Server, Randy K. Nanstad, M. Brumovský
This chapter discusses the fracture toughness of reactor pressure vessel (RPV) materials as a consequence of service in a neutron irradiation environment. Fracture toughness of the materials is directly related to structural integrity of the operatin
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::cd4ad77f648d849a2dd42581bc7a9b92
https://doi.org/10.1533/9780857096470.3.295
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3
Reactor pressure vessel (RPV) design and fabrication: the case of the USA
Autor: W.L. Server, R.K. Nanstad
The general design following the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code and fabrication processes used in the USA for nuclear reactor pressure vessels (RPVs) are described. Also, several RPVs in countries othe
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::a00055a6d44969a738c4c1611da1965d
https://doi.org/10.1533/9780857096470.1.3
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5
Application of the Master Curve in the ASME Code
Autor: W.L Server, Stan T. Rosinski
Publikováno v: International Journal of Pressure Vessels and Piping. 77:591-598
The ASME Code reference toughness curves are based upon an approach that utilizes a material normalizing and indexing parameter, RT NDT . This parameter is based upon the results from Charpy V-notch and drop weight nil-ductility transition temperatur
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::b8ae64d9c5469924bb87096ab514bf0f
https://doi.org/10.1016/s0308-0161(00)00031-4
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6
An aging management approach for pressurized water reactor pressure vessels
Autor: W.L. Server, V.N. Shah
Publikováno v: International Journal of Pressure Vessels and Piping. 54:317-340
This paper presents a generic approach, based on known and established results of aging damage assessments, for evaluating structural integrity and managing aging damage of pressurized water reactor (PWR) pressure vessels during extended operation. T
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::167e8f86c390c159a4518866b0714b31
https://doi.org/10.1016/0308-0161(93)90140-o
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7
Evaluation of Current Procedures for Dynamic Fracture-Toughness Testing
Autor: W.L. Server, R.A. Wullaert, J.W. Sheckherd
Instrumented impact test requirements for impact velocity, inertial loading, time to fracture, and frequency response were developed as a part of a large testing program sponsored by the Electric Power Research Institute (EPRI). These test procedures
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::0fcac6b1da0ec304e24e37c0122fbbe2
https://doi.org/10.1520/stp35554s
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8
Preparation of Reconstituted Charpy V-Notch Impact Specimens for Generating Pressure Vessel Steel Fracture Toughness Data
Autor: E.O. Fromm, W.L. Server, J.S. Perrin, P. McConnell
The arc stud welding process has been adapted for use in producing reconstituted Charpy V-notch impact specimens. In this process, each half of a tested and fractured Charpy specimen is used as the central region of a reconstituted specimen. End tabs
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::f9707a3facbec3fbcac29c9fd9909a4b
https://doi.org/10.1520/stp34367s
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9
Residual Life Assessment of Light Water Reactor Pressure Vessels
Autor: V.N. Shah, A.V. Swaroop, G.R. Odette, W.L. Server
The service-dependent degradation (agina) of light water reactor (LWR) pressure vessels due to irradiation embrittlement is discussed in this paper. The major variable which influence the irradiation embrittlement of LWR vessels are the copper and ni
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::0723f279acc40f04c52073c5b50f3b84
https://doi.org/10.1520/stp10393s
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10
The EPRI embrittlement management program
Autor: T.J. Griesbach, W.L. Server
Publikováno v: Nuclear Engineering and Design. 124:153-156
One of the main concerns in nuclear power plant operation is protecting the reactor pressure vessel against unstable, brittle fracture. The ASME Boiler and Pressure Vessel Code and the Code of Federal Regulations prescribe plant operating pressure—
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::499fa8a501bab80c2515879a9b68fd06
https://doi.org/10.1016/0029-5493(90)90361-z
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