Zobrazeno 1 - 10
of 35
pro vyhledávání: '"Stan T. Rosinski"'
Publikováno v:
IEEE Transactions on Power Systems. 32:157-165
This paper presents a coordinated model predictive control scheme for the Mid-Columbia hydropower system. The Mid-Columbia system consists of seven hydropower plants on the Columbia River in the United States. The state-space model used in the contro
Publikováno v:
Volume 7: Operations, Applications, and Components.
This paper discusses a specially developed semiconductor strain cell that allows sensitive measurement of surface strain in environments with temperatures up to 1050F (566C). There is an unmet industry-wide need in the manufacturing and power generat
Autor:
Stan T. Rosinski, Andres Sanchez, Curt Carney, Ulrich Woerz, Mario Berasi, Kent K. Coleman, Stefano Sigali, Nicola Rossi
Publikováno v:
Volume 7: Operations, Applications and Components.
Coal-fired power plants are often required to cycle extensively and operate relatively infrequently due to power market conditions and an increasingly broad deployment of renewable energy. This cyclic (start-stop and/or fast ramp rate) operation can
Publikováno v:
Volume 6B: Materials and Fabrication.
Although failures of seam welded high-energy piping date to about 1970, the utility industry concern about premature failure of longitudinal seam welded piping has been of the utmost importance since the mid 1980’s driven primarily by well publiciz
Publikováno v:
International Journal of Pressure Vessels and Piping. 79:701-713
The Master Curve fracture toughness approach has been used in the USA for better defining the transition temperature fracture toughness of irradiated reactor pressure vessel (RPV) steels for end-of-life (EOL) and EOL extension (EOLE) time periods. Th
Autor:
Robert O Hardies, Stan T. Rosinski
Publikováno v:
International Journal of Pressure Vessels and Piping. 78:147-153
A joint project is under way between the US nuclear power industry and the US Nuclear Regulatory Commission (NRC) to re-evaluate the pressurized thermal shock (PTS) screening criteria as presently defined in title 10 of the Code of Federal Regulation
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
Autor:
Stan T. Rosinski, Robert Carter
Publikováno v:
Nuclear Engineering and Design. 194:199-204
The demonstration of reactor pressure vessel (RPV) structural integrity is an essential element in ensuring the continued safe and reliable operation of US nuclear power plants. The Electric Power Research Institute (EPRI), through its domestic and i
Publikováno v:
Materials Transactions, JIM. 40:320-327
The objective of this study is to clarify the effects of pre-cycling above the fatigue limit on near the fatigue-limit fatigue behaviors of SA508, low alloy steel for nuclear pressure vessels, correlating fatigue lifetime with microstructural changes
Autor:
Stan T. Rosinski
Publikováno v:
Nuclear Engineering and Design. 181:251-255
Fatigue has been identified as a technical issue potentially affecting the license renewal of nuclear power plants. The NEI License Renewal Industry Reports (IRs) maintained that the current fatigue licensing basis (CFLB) is adequate to manage the ef