The Experts below are selected from a list of 159 Experts worldwide ranked by ideXlab platform
Burtron H Davis - One of the best experts on this subject based on the ideXlab platform.
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fischer tropsch synthesis overview of Reactor Development and future potentialities
Topics in Catalysis, 2005Co-Authors: Burtron H DavisAbstract:An overview of the Reactors utilized for the Fischer–Tropsch synthesis is considered during three time periods: discovery to 1945, 1945–1970, and 1970 to date. A brief outline of the scientific and engineering Developments related to chemical Reactor design for the same three periods is also presented. In general, the Reactor Developments outpaced the ability to utilize the scientific and engineering advances on the academic level. However, today it appears that the academic and industrial Developments closely match each other in content and interests. Even so, the availability of reliable data from large-scale pilot plants and/or commercial operations remain available only to the organization developing the data.
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Fischer–Tropsch synthesis: Overview of Reactor Development and future potentialities
Topics in Catalysis, 2005Co-Authors: Burtron H DavisAbstract:An overview of the Reactors utilized for the Fischer–Tropsch synthesis is considered during three time periods: discovery to 1945, 1945–1970, and 1970 to date. A brief outline of the scientific and engineering Developments related to chemical Reactor design for the same three periods is also presented. In general, the Reactor Developments outpaced the ability to utilize the scientific and engineering advances on the academic level. However, today it appears that the academic and industrial Developments closely match each other in content and interests. Even so, the availability of reliable data from large-scale pilot plants and/or commercial operations remain available only to the organization developing the data.
Nariaki Uto - One of the best experts on this subject based on the ideXlab platform.
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A summary of sodium-cooled fast Reactor Development
Progress in Nuclear Energy, 2014Co-Authors: Kazumi Aoto, Robert Hill, Philippe Dufour, Yang Hongyi, Jean Paul Glatz, Yeong-il Kim, Yury Ashurko, Nariaki UtoAbstract:Abstract Much of the basic technology for the Sodium-cooled fast Reactor (SFR) has been established through long term Development experience with former fast Reactor programs, and is being confirmed by the Phenix end-of-life tests in France, the restart of Monju in Japan, the lifetime extension of BN-600 in Russia, and the startup of the China Experimental Fast Reactor in China. Planned startup in 2014 for new SFRs: BN-800 in Russia and PFBR in India, will further enhance the confirmation of the SFR basic technology. Nowadays, the SFR Development has advanced to aiming at establishment of the Generation-IV system which is dedicated to sustainable energy generation and actinide management, and several advanced SFR concepts are under Development such as PRISM, JSFR, ASTRID, PGSFR, BN-1200, and CFR-600. Generation-IV International Forum is an international collaboration framework where various R&D activities are progressing on design of system and component, safety and operation, advanced fuel, and actinide cycle for the Generation-IV SFR Development, and will play a beneficial role of promoting them thorough providing an opportunity to share the past experience and the latest data of design and R&D among countries developing SFR.
R.w. Moir - One of the best experts on this subject based on the ideXlab platform.
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Recommendations for a restart of molten salt Reactor Development
Energy Conversion and Management, 2008Co-Authors: R.w. MoirAbstract:Abstract The concept of the molten salt Reactor (MSR) refuses to go away. The Generation-IV process lists the MSR as one of the six concepts to be considered for extending fuel resources. Good fuel utilization and good economics are required to meet the often-cited goal of 10 TWe globally and 1 TWe for the US by non-carbon energy sources in this century by nuclear fission. Strong incentives for the molten salt Reactor design are its good fuel utilization, good economics, amazing fuel flexibility and promised large benefits. It can: • use thorium or uranium; • be designed with lots of graphite to have a fairly thermal neutron spectrum or without graphite moderator to have an epithermal neutron spectrum; • fission uranium isotopes and plutonium isotopes; • produces less long-lived wastes than today’s Reactors by a factor of 10–100; • operate with non-weapon grade fissile fuel, or in suitable sites it can operate with enrichment between Reactor-grade and weapon grade fissile fuel; • be a breeder or near breeder; • operate at temperature >1100 °C if carbon composites are successfully developed. Enhancing 232U content in the uranium to over 500 ppm makes the fuel undesirable for weapons, but it should not detract from its economic use in liquid fuel Reactors: a big advantage in nonproliferation. Economics of the MSR are enhanced by operating at low pressure and high temperature and may even lead to the preferred route to hydrogen production. The cost of the electricity produced from low enriched fuel averaged over the life of the entire process, has been predicted to be about 10% lower than that from LWRs, and 20% lower for high-enriched fuel, with uncertainties of about 10%. The Development cost has been estimated at about 1 B$ (e.g., a 100 M$/year base program for 10 years) not including construction of a series of Reactors leading up to the deployment of multiple commercial units at an assumed cost of 9 B$ (450 M$/year over 20 years). A benefit of liquid fuel is that smaller power Reactors can faithfully test features of larger Reactors, thereby reducing the number of steps to commercial deployment. Assuming electricity is worth $ 50 per MWe h, then 50 years of 10 TWe power level would be worth 200 trillion dollars. If the MSR could be developed and proven for 10 B$ and would save 10% over its alternative, the total savings over 50 years would be 20 trillion dollars: a good return on investment even considering discounted future savings. The incentives for the molten salt Reactor are so strong and its relevance to our energy policy and national security are so compelling that one asks, “Why has the Reactor not already been developed?”
Kazumi Aoto - One of the best experts on this subject based on the ideXlab platform.
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A summary of sodium-cooled fast Reactor Development
Progress in Nuclear Energy, 2014Co-Authors: Kazumi Aoto, Robert Hill, Philippe Dufour, Yang Hongyi, Jean Paul Glatz, Yeong-il Kim, Yury Ashurko, Nariaki UtoAbstract:Abstract Much of the basic technology for the Sodium-cooled fast Reactor (SFR) has been established through long term Development experience with former fast Reactor programs, and is being confirmed by the Phenix end-of-life tests in France, the restart of Monju in Japan, the lifetime extension of BN-600 in Russia, and the startup of the China Experimental Fast Reactor in China. Planned startup in 2014 for new SFRs: BN-800 in Russia and PFBR in India, will further enhance the confirmation of the SFR basic technology. Nowadays, the SFR Development has advanced to aiming at establishment of the Generation-IV system which is dedicated to sustainable energy generation and actinide management, and several advanced SFR concepts are under Development such as PRISM, JSFR, ASTRID, PGSFR, BN-1200, and CFR-600. Generation-IV International Forum is an international collaboration framework where various R&D activities are progressing on design of system and component, safety and operation, advanced fuel, and actinide cycle for the Generation-IV SFR Development, and will play a beneficial role of promoting them thorough providing an opportunity to share the past experience and the latest data of design and R&D among countries developing SFR.
Yeong-il Kim - One of the best experts on this subject based on the ideXlab platform.
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A summary of sodium-cooled fast Reactor Development
Progress in Nuclear Energy, 2014Co-Authors: Kazumi Aoto, Robert Hill, Philippe Dufour, Yang Hongyi, Jean Paul Glatz, Yeong-il Kim, Yury Ashurko, Nariaki UtoAbstract:Abstract Much of the basic technology for the Sodium-cooled fast Reactor (SFR) has been established through long term Development experience with former fast Reactor programs, and is being confirmed by the Phenix end-of-life tests in France, the restart of Monju in Japan, the lifetime extension of BN-600 in Russia, and the startup of the China Experimental Fast Reactor in China. Planned startup in 2014 for new SFRs: BN-800 in Russia and PFBR in India, will further enhance the confirmation of the SFR basic technology. Nowadays, the SFR Development has advanced to aiming at establishment of the Generation-IV system which is dedicated to sustainable energy generation and actinide management, and several advanced SFR concepts are under Development such as PRISM, JSFR, ASTRID, PGSFR, BN-1200, and CFR-600. Generation-IV International Forum is an international collaboration framework where various R&D activities are progressing on design of system and component, safety and operation, advanced fuel, and actinide cycle for the Generation-IV SFR Development, and will play a beneficial role of promoting them thorough providing an opportunity to share the past experience and the latest data of design and R&D among countries developing SFR.
