The Experts below are selected from a list of 137559 Experts worldwide ranked by ideXlab platform
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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cycle chemistry and its effect on Materials in a supercritical water cooled reactor a synthesis of current understanding
Corrosion Science, 2012Co-Authors: David Guzonas, W CookAbstract:Abstract Interest in Materials Degradation in supercritical water (SCW) increased significantly after the Generation IV International Forum selected the supercritical water-cooled reactor as one of six concepts for investigation. While a significant body of literature now exists on alloy corrosion in SCW, most studies have focused on the metal side of the metal–water interface. Using new data and a selective review of corrosion in SCW, this paper highlights how changes in SCW density change the corrosion mechanism, and highlights the close link between corrosion in SCW and high-temperature steam above 500 °C. Key issues in test methodologies are also discussed.
Juan M Coronado - One of the best experts on this subject based on the ideXlab platform.
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assessing cr incorporation in mn2o3 mn3o4 redox Materials for thermochemical heat storage applications
Journal of energy storage, 2021Co-Authors: Alfonso J Carrillo, Patricia Pizarro, Juan M CoronadoAbstract:Abstract Widening the use of renewable sources requires more efficient energy storage systems to overcome the inherent intermittence of solar energy. In this respect, thermal energy storage coupled to concentrated solar power represents an inexpensive technology to achieve that goal. In particular, the use of reversible thermochemical reactions is promising due to a higher energy storage density if compared with commercial sensible heat storage on molten salts. However, some of these systems that rely on gas-solid reactions can suffer a cycle-to-cycle loss of activity due to slow kinetics and Materials Degradation, which is detrimental for its potential future commercialization. In this work, we have assessed the incorporation of Cr cations in the redox couple Mn2O3/Mn3O4, as a way to stabilize the multi-cyclic activity over prolonged operation at high temperatures (650-1000 °C). Reduction has been studied with in situ XRD and kinetic analyses, which confirm that Cr incorporation shifts the reaction towards high temperatures. Long term redox cycling tests confirm that 5% Cr incorporation helps to stabilize the redox activity of Mn2O3/Mn3O4.
Patricia Pizarro - One of the best experts on this subject based on the ideXlab platform.
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assessing cr incorporation in mn2o3 mn3o4 redox Materials for thermochemical heat storage applications
Journal of energy storage, 2021Co-Authors: Alfonso J Carrillo, Patricia Pizarro, Juan M CoronadoAbstract:Abstract Widening the use of renewable sources requires more efficient energy storage systems to overcome the inherent intermittence of solar energy. In this respect, thermal energy storage coupled to concentrated solar power represents an inexpensive technology to achieve that goal. In particular, the use of reversible thermochemical reactions is promising due to a higher energy storage density if compared with commercial sensible heat storage on molten salts. However, some of these systems that rely on gas-solid reactions can suffer a cycle-to-cycle loss of activity due to slow kinetics and Materials Degradation, which is detrimental for its potential future commercialization. In this work, we have assessed the incorporation of Cr cations in the redox couple Mn2O3/Mn3O4, as a way to stabilize the multi-cyclic activity over prolonged operation at high temperatures (650-1000 °C). Reduction has been studied with in situ XRD and kinetic analyses, which confirm that Cr incorporation shifts the reaction towards high temperatures. Long term redox cycling tests confirm that 5% Cr incorporation helps to stabilize the redox activity of Mn2O3/Mn3O4.
D Terentyev - One of the best experts on this subject based on the ideXlab platform.
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interatomic potential for studying ageing under irradiation in stainless steels the fenicr model alloy
Modelling and Simulation in Materials Science and Engineering, 2013Co-Authors: G Bonny, N Castin, D TerentyevAbstract:The Degradation of austenitic stainless steels in a radiation environment is a known problem for the in-core components of nuclear light water reactors. For a better understanding of the prevailing mechanisms responsible for the Materials' Degradation, large-scale atomistic simulations are desirable. In this framework and as a follow-up on Bonny et al (2011 Modelling Simul. Mater. Sci. Eng. 19 085008), we developed an embedded atom method type interatomic potential for the ternary FeNiCr system to model the production and evolution of radiation defects. Special attention has been drawn to the Fe10Ni20Cr alloy, whose properties were ensured to be close to those of 316L austenitic stainless steels. The potential is extensively benchmarked against density functional theory calculations and the potential developed in our earlier work. As a first validation, the potential is used in AKMC simulations to simulate thermal annealing experiments in order to determine the self-diffusion coefficients of the components in FeNiCr alloys around the Fe10Ni20Cr composition. The results from these simulations are consistent with experiments, i.e., DCr > DNi > DFe.
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interatomic potential to study plasticity in stainless steels the fenicr model alloy
Modelling and Simulation in Materials Science and Engineering, 2011Co-Authors: G Bonny, D Terentyev, R C Pasianot, Samuel Ponce, A BakaevAbstract:Austenitic stainless steels are commonly used Materials for in-core components of nuclear light water reactors. In service, such components are exposed to harsh conditions: intense neutron irradiation, mechanical and thermal stresses, and aggressive corrosion environment which all contribute to the components' Degradation. For a better understanding of the prevailing mechanisms responsible for the Materials Degradation, large-scale atomistic simulations are desirable. In this framework we developed an embedded atom method type interatomic potential for the ternary FeNiCr system to model movement of dislocations and their interaction with radiation defects. Special attention has been drawn to the Fe–10Ni–20Cr alloy, whose properties were ensured to be close to those of 316L austenitic stainless steel. In particular, the stacking fault energy and elastic constants are well reproduced. The fcc phase for the Fe–10Ni–20Cr random alloy was proven to be stable in the temperature range 0–900 K and under shear strain up to 5%. For the same alloy the stable glide of screw dislocations and stability of Frank loops was confirmed.
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.
