The Experts below are selected from a list of 19239 Experts worldwide ranked by ideXlab platform
Zaki Suud - One of the best experts on this subject based on the ideXlab platform.
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local blockage analysis of lead cooled next generation Nuclear Power Reactors
International Journal of Nuclear Energy Science and Technology, 2010Co-Authors: Zaki Suud, Hiroshi SekimotoAbstract:Local blockage is one of the possible severe accidents which may occur in lead (Pb)- or lead-bismuth (Pb-Bi)-cooled fast Reactors due to their high melting temperature. In a local blockage accident, the local temperature increase cannot significantly reduce Power level inherently. Therefore, this type of accident should be considered in the core design optimisation of those Reactors. In the present study, a local blockage accident analysis of Pb-Bi-cooled long-life fast Reactors has been performed. In this analysis, we consider two models. In the first model, we consider that the cross-flow can only come from two nearby channels. In the second model, we consider that the cross-flow can come from four nearby channels. The results show that for the present long-life Pb-Bi Reactors which are of medium Power density level, local blockage will increase the coolant, cladding and pellet temperatures but still within their limits.
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the prospect of mox fuel based pbbi cooled small Nuclear Power Reactors
Progress in Nuclear Energy, 2005Co-Authors: Zaki Suud, Bakrie Arbie, S SedyartomoAbstract:Abstract Safety performance of MOX fuel based Pb Bi cooled small fast Power Reactors has been analyzed and discussed. Though the thermal conductivity of MOX fuel is not large relative to that of nitride or metal fuel, but by proper combination of relatively small Power density and relatively large natural circulation it can compensate fuel temperature decrease with coolant temperature increase smartly during unprotected loss of flow accident. Under such condition, accident analysis discussed in this paper show that under unprotected total loss of flow (ULOF) accident the reactor can survive inherently using combination of reactivity feedback. For unprotected rod run out transient over Power (UTOP) accident the MOX reactor can overcome external reactivity by smaller Power increase compared to that of nitride fueled Reactors case. In this case doppler feedback plays much more important role compared to radial expansion component. So the MOX fueled small Power Reactors discussed here can survive both UTOP and ULOF accident with still enough temperature margin.
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design study of lead and lead bismuth cooled small long life Nuclear Power Reactors using metallic and nitride fuel
Nuclear Technology, 1995Co-Authors: Hiroshi Sekimoto, Zaki SuudAbstract:AbstractA conceptual design study of small long-life Nuclear Power Reactors used for a remote or isolated area has been performed. Lead as well as lead-bismuth is employed as the coolant, and both metallic and nitride fuels are investigated. There are some severe requirements on these Reactors for operability, maintainability, safety, and proliferation resistance. Some important characteristics of the proposed designs [150 MW(thermal)] are the following: transportability between reactor factory and operation site; capability of long-life operation (12 yr) without refueling or fuel shuffling while maintaining burnup reactivity swing less than 0.1% Δk; negative total core coolant void coefficient of reactivity over all the burnup period; omission of intermediate heat exchanger; and a relatively large contribution of natural circulation.
Imad Khamis - One of the best experts on this subject based on the ideXlab platform.
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heat pipes as an extra measure to eliminate radioactive contamination in Nuclear seawater desalination
Desalination and Water Treatment, 2010Co-Authors: Imad Khamis, Vladimir AnastasovAbstract:Reduction in tritium contamination levels in the product water is a top priority for gaining public confidence in Nuclear seawater desalination. Hence, the search for new technologies, to enable such reduction is an ongoing process. Heat pipes are seen as a promising technology to achieve such goal. In fact, concern over possible contamination of the product water could well be eliminated using this technology. Utilising new designs for desalination heat exchangers based on the heat pipe technology will add an extra loop, which will prevent direct contact between the Nuclear and the product water loops under normal and anticipated operational failure occurrences. As a result, heat pipes can play a decisive role in enhancing public perception of Nuclear desalination in particular and seawater desalination in general. When coupled to the Low-Temperature Multi-Effect Distillation process, heat pipes based heat exchangers could harness waste-heat generated in Nuclear Power Reactors and effectively improve the...
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potential of heat pipe technology in Nuclear seawater desalination
Desalination, 2009Co-Authors: Vladimir Anastasov, Imad KhamisAbstract:Heat pipe technology may play a decisive role in improving the overall economics, and public perception on Nuclear desalination, specifically on seawater desalination. When coupled to the Low-Temperature Multi-Effect Distillation process, heat pipes could effectively harness most of the waste heat generated in various types of Nuclear Power Reactors. Indeed, the potential application of heat pipes could be seen as a viable option to Nuclear seawater desalination where the efficiency to harness waste heat might not only be enhanced to produce larger quantities of potable water, but also to reduce the environmental impact of Nuclear desalination process. Furthermore, the use of heat pipe-based heat recovery systems in desalination plant may improve the overall thermodynamics of the desalination process, as well as help to ensure that the product water is free from any contamination which occur under normal process, thus preventing operational failure occurrences as this would add an extra loop preventing direct contact between radiation and the produced water. In this paper, a new concept for Nuclear desalination system based on heat pipe technology is introduced and the anticipated reduction in the tritium level resulting from the use of heat pipe systems is discussed.
Vladimir Anastasov - One of the best experts on this subject based on the ideXlab platform.
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POTENTIAL OF HEAT PIPE TECHNOLOGY IN Nuclear SEAWATER DESALINATION 1
2014Co-Authors: Hussam Jouhara, Vladimir Anastasov, Ibrahim KhamisAbstract:Heat pipe technology may play a decisive role in improving the overall economics, and public perception on Nuclear desalination, specifically on seawater desalination. When coupled to the Low-Temperature Multi-Effect Distillation process, heat pipes could effectively harness most of the waste heat generated in various types of Nuclear Power Reactors. Indeed, the potential application of heat pipes could be seen as a viable option to Nuclear seawater desalination where the efficiency to harness waste heat might not only be enhanced to produce larger quantities of potable water, but also to reduce the environmental impact of Nuclear desalination process. Furthermore, the use of heat pipes-based heat recovery systems in desalination plant may improve the overall thermodynamics of the desalination process, as well as help to ensure that the product water is free from any contamination which occur under normal process, thus preventing operational failure occurrences as this would add an extra loop preventing direct contact between radiation and the produced water. In this paper, a new concept for Nuclear desalination system based on heat pipe technology is introduced and the anticipated reduction in the tritium level resulting from the use of heat pipe systems is discussed
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heat pipes as an extra measure to eliminate radioactive contamination in Nuclear seawater desalination
Desalination and Water Treatment, 2010Co-Authors: Imad Khamis, Vladimir AnastasovAbstract:Reduction in tritium contamination levels in the product water is a top priority for gaining public confidence in Nuclear seawater desalination. Hence, the search for new technologies, to enable such reduction is an ongoing process. Heat pipes are seen as a promising technology to achieve such goal. In fact, concern over possible contamination of the product water could well be eliminated using this technology. Utilising new designs for desalination heat exchangers based on the heat pipe technology will add an extra loop, which will prevent direct contact between the Nuclear and the product water loops under normal and anticipated operational failure occurrences. As a result, heat pipes can play a decisive role in enhancing public perception of Nuclear desalination in particular and seawater desalination in general. When coupled to the Low-Temperature Multi-Effect Distillation process, heat pipes based heat exchangers could harness waste-heat generated in Nuclear Power Reactors and effectively improve the...
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potential of heat pipe technology in Nuclear seawater desalination
Desalination, 2009Co-Authors: Vladimir Anastasov, Imad KhamisAbstract:Heat pipe technology may play a decisive role in improving the overall economics, and public perception on Nuclear desalination, specifically on seawater desalination. When coupled to the Low-Temperature Multi-Effect Distillation process, heat pipes could effectively harness most of the waste heat generated in various types of Nuclear Power Reactors. Indeed, the potential application of heat pipes could be seen as a viable option to Nuclear seawater desalination where the efficiency to harness waste heat might not only be enhanced to produce larger quantities of potable water, but also to reduce the environmental impact of Nuclear desalination process. Furthermore, the use of heat pipe-based heat recovery systems in desalination plant may improve the overall thermodynamics of the desalination process, as well as help to ensure that the product water is free from any contamination which occur under normal process, thus preventing operational failure occurrences as this would add an extra loop preventing direct contact between radiation and the produced water. In this paper, a new concept for Nuclear desalination system based on heat pipe technology is introduced and the anticipated reduction in the tritium level resulting from the use of heat pipe systems is discussed.
Hiroshi Sekimoto - One of the best experts on this subject based on the ideXlab platform.
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local blockage analysis of lead cooled next generation Nuclear Power Reactors
International Journal of Nuclear Energy Science and Technology, 2010Co-Authors: Zaki Suud, Hiroshi SekimotoAbstract:Local blockage is one of the possible severe accidents which may occur in lead (Pb)- or lead-bismuth (Pb-Bi)-cooled fast Reactors due to their high melting temperature. In a local blockage accident, the local temperature increase cannot significantly reduce Power level inherently. Therefore, this type of accident should be considered in the core design optimisation of those Reactors. In the present study, a local blockage accident analysis of Pb-Bi-cooled long-life fast Reactors has been performed. In this analysis, we consider two models. In the first model, we consider that the cross-flow can only come from two nearby channels. In the second model, we consider that the cross-flow can come from four nearby channels. The results show that for the present long-life Pb-Bi Reactors which are of medium Power density level, local blockage will increase the coolant, cladding and pellet temperatures but still within their limits.
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design study of lead and lead bismuth cooled small long life Nuclear Power Reactors using metallic and nitride fuel
Nuclear Technology, 1995Co-Authors: Hiroshi Sekimoto, Zaki SuudAbstract:AbstractA conceptual design study of small long-life Nuclear Power Reactors used for a remote or isolated area has been performed. Lead as well as lead-bismuth is employed as the coolant, and both metallic and nitride fuels are investigated. There are some severe requirements on these Reactors for operability, maintainability, safety, and proliferation resistance. Some important characteristics of the proposed designs [150 MW(thermal)] are the following: transportability between reactor factory and operation site; capability of long-life operation (12 yr) without refueling or fuel shuffling while maintaining burnup reactivity swing less than 0.1% Δk; negative total core coolant void coefficient of reactivity over all the burnup period; omission of intermediate heat exchanger; and a relatively large contribution of natural circulation.
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Design study of lead- and lead-bismuth-cooled small long-life Nuclear Power Reactors using metallic and nitride fuel
Nuclear Technology, 1995Co-Authors: Hiroshi Sekimoto, Zaki Su’udAbstract:A conceptual design study of small long-life Nuclear Power Reactors used for a remote or isolated area has been performed. Lead as well as lead-bismuth is employed as the coolant, and both metallic...
Zaki Su’ud - One of the best experts on this subject based on the ideXlab platform.
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Design Study of Small Pb-Bi Cooled Non-Refueling Nuclear Power Reactors (SPINNORs)
Applied Mechanics and Materials, 2012Co-Authors: Zaki Su’udAbstract:Small Pb-Bi Cooled Non-refueling Nuclear Power Reactors(SPINNORs) are small lead-bismuth cooled Nuclear Power Reactors with fast neutron spectrum that could be operated for 20 years without on-site refuelling. In this study the results of neutronic design for 62.5-250MWt NPPs are discussed. The reactor cores are designed to have near zero (less then one effective delayed neutron fraction) burn-up reactivity swing during the burn-up period to avoid a possibility of super-prompt critical accident. The basic concept is that the reactor core is adjusted so that its internal conversion ratio is nearly one. During the reactor operation fissile material accumulates in this central region, which helps to compensate fissile material loss in the peripheral core region and also contributes to negative coolant loss reactivity effect. In general higher fuel volume fraction is needed for smaller core.
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Design study of lead- and lead-bismuth-cooled small long-life Nuclear Power Reactors using metallic and nitride fuel
Nuclear Technology, 1995Co-Authors: Hiroshi Sekimoto, Zaki Su’udAbstract:A conceptual design study of small long-life Nuclear Power Reactors used for a remote or isolated area has been performed. Lead as well as lead-bismuth is employed as the coolant, and both metallic...
