The Experts below are selected from a list of 201 Experts worldwide ranked by ideXlab platform
R. Novotny - One of the best experts on this subject based on the ideXlab platform.
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Supercritical water-cooled Reactor Materials – Summary of research and open issues
Progress in Nuclear Energy, 2014Co-Authors: David Guzonas, R. NovotnyAbstract:Abstract The Supercritical Water Reactor (SCWR) is one of the six Reactor concepts being investigated under the framework of the Generation IV International Forum (GIF). Research on Materials and chemistry for supercritical water-cooled Reactors dates back to the 1960s when a number of Reactor concepts using water at supercritical temperatures but sub-critical pressures (nuclear steam) were studied. There is also significant experience available from the operation of supercritical fossil-fired power plants. In this paper, the Materials requirements of the various SCWR concepts are introduced, with a focus on the European Union pressure vessel concept and the Canadian pressure tube concept. The current understanding of the key Materials degradation issues is reviewed, and knowledge gaps identified.
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supercritical water cooled Reactor Materials summary of research and open issues
Progress in Nuclear Energy, 2014Co-Authors: David Guzonas, R. NovotnyAbstract:Abstract The Supercritical Water Reactor (SCWR) is one of the six Reactor concepts being investigated under the framework of the Generation IV International Forum (GIF). Research on Materials and chemistry for supercritical water-cooled Reactors dates back to the 1960s when a number of Reactor concepts using water at supercritical temperatures but sub-critical pressures (nuclear steam) were studied. There is also significant experience available from the operation of supercritical fossil-fired power plants. In this paper, the Materials requirements of the various SCWR concepts are introduced, with a focus on the European Union pressure vessel concept and the Canadian pressure tube concept. The current understanding of the key Materials degradation issues is reviewed, and knowledge gaps identified.
David Guzonas - One of the best experts on this subject based on the ideXlab platform.
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Supercritical water-cooled Reactor Materials – Summary of research and open issues
Progress in Nuclear Energy, 2014Co-Authors: David Guzonas, R. NovotnyAbstract:Abstract The Supercritical Water Reactor (SCWR) is one of the six Reactor concepts being investigated under the framework of the Generation IV International Forum (GIF). Research on Materials and chemistry for supercritical water-cooled Reactors dates back to the 1960s when a number of Reactor concepts using water at supercritical temperatures but sub-critical pressures (nuclear steam) were studied. There is also significant experience available from the operation of supercritical fossil-fired power plants. In this paper, the Materials requirements of the various SCWR concepts are introduced, with a focus on the European Union pressure vessel concept and the Canadian pressure tube concept. The current understanding of the key Materials degradation issues is reviewed, and knowledge gaps identified.
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supercritical water cooled Reactor Materials summary of research and open issues
Progress in Nuclear Energy, 2014Co-Authors: David Guzonas, R. NovotnyAbstract:Abstract The Supercritical Water Reactor (SCWR) is one of the six Reactor concepts being investigated under the framework of the Generation IV International Forum (GIF). Research on Materials and chemistry for supercritical water-cooled Reactors dates back to the 1960s when a number of Reactor concepts using water at supercritical temperatures but sub-critical pressures (nuclear steam) were studied. There is also significant experience available from the operation of supercritical fossil-fired power plants. In this paper, the Materials requirements of the various SCWR concepts are introduced, with a focus on the European Union pressure vessel concept and the Canadian pressure tube concept. The current understanding of the key Materials degradation issues is reviewed, and knowledge gaps identified.
Á. Horváth - One of the best experts on this subject based on the ideXlab platform.
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Mössbauer study of EUROFER and VVER steel Reactor Materials
Hyperfine Interactions, 2012Co-Authors: Erno Kuzmann, Á. Horváth, L. Alves, José Felipe Costa Da Silva, Uilame Umbelino Gomes, Carlson Pereira De Souza, Zoltán HomonnayAbstract:57Fe Mossbauer spectroscopy and X-ray diffractometry were used to study EUROFER or VVER ferritic Reactor steels mechanically alloyed with TaC or NbC. Significant changes were found in the Mossbauer spectra and in the corresponding hyperfine field distributions between the ball milled pure steel and that alloyed with TaC or NbC. Spectral differences were also found in the case of use of same carbides with different origin, too. The observed spectral changes as an effect of ball milling of the Reactor material steels with carbides can be associated with change in short range order of the constituents of steel.
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Magnetic measurements for evaluation of radiation damage on nuclear Reactor Materials
Nuclear Engineering and Design, 2010Co-Authors: S. Pirfo Barroso, M. Horváth, Á. HorváthAbstract:It is important for the plant lifetime management to estimate the loss of toughness and other effects, e.g. increase of yield strength and hardness, caused by irradiation. This paper deals with the use of magnetic measurements to determine the irradiation effects on nuclear Reactor structural Materials. Three types of nuclear Reactor Materials were studied. Samples of the Materials were irradiated with different neutron fluences. The Magnetic Barkhausen Emission was measured using stabilised flux mode, i.e., control of the magnetic flux within the sample to compensate for leakage and variations on the flux. The samples were carefully identified according to position and the cutting direction within the steel forging block. Anisotropy effect due to sample cutting direction was observed and it masks the magnetic signal results induced by the irradiation effects. The results on the specimens cut in the same direction shows correlation with irradiation induced material hardening and its dependence on fluence. Different Materials show different hardening levels. Barkhausen emission results were correlated to neutron fluence taking into account the cutting direction.
Zoltán Homonnay - One of the best experts on this subject based on the ideXlab platform.
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Mössbauer study of EUROFER and VVER steel Reactor Materials
Hyperfine Interactions, 2012Co-Authors: Erno Kuzmann, Á. Horváth, L. Alves, José Felipe Costa Da Silva, Uilame Umbelino Gomes, Carlson Pereira De Souza, Zoltán HomonnayAbstract:57Fe Mossbauer spectroscopy and X-ray diffractometry were used to study EUROFER or VVER ferritic Reactor steels mechanically alloyed with TaC or NbC. Significant changes were found in the Mossbauer spectra and in the corresponding hyperfine field distributions between the ball milled pure steel and that alloyed with TaC or NbC. Spectral differences were also found in the case of use of same carbides with different origin, too. The observed spectral changes as an effect of ball milling of the Reactor material steels with carbides can be associated with change in short range order of the constituents of steel.
N.g. Awadalla - One of the best experts on this subject based on the ideXlab platform.
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Reactor Material Program Fracture Toughness of Type 304 Stainless Steel
2001Co-Authors: N.g. AwadallaAbstract:This report describes the experimental procedure for Type 304 Stainless Steel fracture toughness measurements and the application of results. Typical toughness values are given based on the completed test program for the Reactor Materials Program (RMP). Test specimen size effects and limitations of the applicability in the fracture mechanics methodology are outlined as well as a brief discussion on irradiation effects.
