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Author: Publisher: ISBN: Category : Languages : en Pages : 8
Book Description
During the ITER design phase, the conceptual design of the fuel processing cycle has been established. The fuel processing cycle is designed to be able to handle all the tritium containing streams of the ITER. These streams include plasma exhaust, blanket tritium recovery, pellet propellant, neutron beam exhaust, water coolant detritiation, waste water from the room air detritiation system. The design is very conservative, i.e., the flow rate of each stream is high and the detritiation factor required is very high. A preliminary optimization study has been carried out to simplify the ITER fuel cycle design. We investigated: The throughput and composition of the input tritium containing streams from various components to the fuel processing cycle. The fraction of those streams needed to be detritiated. The required detritiation factors required for each of the streams. The results of the investigation determined that the major input tritium containing steams can be reduced by at least a factor of 10. The required detritiation factor can be reduced from a factor of 100 to 106. The size of the fuel processing cycle, the tritium inventory and the complexity of this system can, therefore, also be reduced.
Author: Publisher: ISBN: Category : Languages : en Pages : 8
Book Description
During the ITER design phase, the conceptual design of the fuel processing cycle has been established. The fuel processing cycle is designed to be able to handle all the tritium containing streams of the ITER. These streams include plasma exhaust, blanket tritium recovery, pellet propellant, neutron beam exhaust, water coolant detritiation, waste water from the room air detritiation system. The design is very conservative, i.e., the flow rate of each stream is high and the detritiation factor required is very high. A preliminary optimization study has been carried out to simplify the ITER fuel cycle design. We investigated: The throughput and composition of the input tritium containing streams from various components to the fuel processing cycle. The fraction of those streams needed to be detritiated. The required detritiation factors required for each of the streams. The results of the investigation determined that the major input tritium containing steams can be reduced by at least a factor of 10. The required detritiation factor can be reduced from a factor of 100 to 106. The size of the fuel processing cycle, the tritium inventory and the complexity of this system can, therefore, also be reduced.
Author: O. K. Kveton Publisher: ISBN: Category : Languages : en Pages : 0
Book Description
Zircaloy-4 fuel sheath specimens 15.2 mm diameter by 0.42 mm wall thickness with beryllium-brazed appendages have been laboratory tested at high temperature with internal gas pressurization and inert gas shielding of the outer surfaces. with sufficient hoop stress at temperatures less than 1073 k cracks, which were due to a beryllium assisted crack penetration mechanism, were found to occur at the appendages. formulae to predict the beryllium penetration and rupture have been derived by westinghouse canada ltd. based on data from direct resistance-heated specimens. the formulae are thought to be able to predict the phenomenon in fuel sheaths with changing temperature/pressure histories. a series of tests was done by canadian general electric to determine the formulae ability to predict the occurrence of beryllium assisted crack penetration in specimens heated indirectly with internal heaters. the tests showed: 1) there is an incubation period before any beryllium assisted crack penetration occurs. 2) at sheath temperatures below approximately equal to 1073 k sheath rupture by excessive mechanical strain will preclude rupture by beryllium assisted crack penetration. 3) the formulae predicted rupture times above and below the braze alloy melting temperature within the previously determined confidence limits. 4) predictions of beryllium assisted crack penetration rupture for specimens with changing temperature/pressure histories were of similar accuracy to predictions of isothermal tests. 5) specimens with an appendage plane of one bearing pad and three spacer pads behaved similarly to the specimens with four spacer pads on which the formulae were based.
Author: National Academies of Sciences Engineering and Medicine Publisher: ISBN: 9780309685382 Category : Languages : en Pages :
Book Description
Fusion energy offers the prospect of addressing the nation's energy needs and contributing to the transition to a low-carbon emission electrical generation infrastructure. Technology and research results from U.S. investments in the major fusion burning plasma experiment known as ITER, coupled with a strong foundation of research funded by the Department of Energy (DOE), position the United States to begin planning for its first fusion pilot plant. Strong interest from the private sector is an additional motivating factor, as the process of decarbonizing and modernizing the nation's electric infrastructure accelerates and companies seek to lead the way. At the request of DOE, Bringing Fusion to the U.S. Grid builds upon the work of the 2019 report Final Report of the Committee on a Strategic Plan for U.S. Burning Plasma Research to identify the key goals and innovations - independent of confinement concept - that are needed to support the development of a U.S. fusion pilot plant that can serve as a model for producing electricity at the lowest possible capital cost.
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Author: O. K. Kveton
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Author: O. K. Kveton
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Author: D. Leger
Author: International Atomic Energy Agency
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Author: National Academies of Sciences Engineering and Medicine