Results 21 to 30 of about 36,342 (264)
Nuclear Energy and Technology, 2015 Mixed nitride uranium–plutonium fuel is the most attractive and advanced type of fuel for fast-neutron sodium-cooled reactors, and is considered as the base fuel for future commercial fast-neutron power reactors.
V.I. Matveev +2 more
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Quantification of polybrominated diphenylethers in oil produced by pyrolysis of flame retarded plastic [PDF]
, 2008 In recent years, there has been extensive research into using pyrolysis to convert toxic brominated plastics into safe, bromine free fuels. However, there has been little investigation of the polybrominated diphenyl ethers (PBDE) that are present in ...
Hall, W.J., Williams, P.T.
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Sodium purification systems for NPP with fast reactors (retrospective and perspective views)
Nuclear Energy and Technology, 2016 Coolant purification systems constitute integral element of any reactor facility. A number of new tasks emerge in the current day reactor engineering, one of which is the task to enhance productivity and capacity of such systems.
F.A. Kozlov +2 more
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Application of genetic algorithms in optimization of SFR nuclear reactor design
Nukleonika, 2021 This work presents a demonstrational application of genetic algorithms (GAs) to solve sample optimization problems in the generation IV nuclear reactor core design.
Żurkowski Wojciech +3 more
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Nuclear Engineering and Technology, 2022 The sodium-cooled fast reactor is among the innovative nuclear technologies selected in the framework of the development of Generation IV concepts, allowing the irradiation of uranium-plutonium mixed oxide fuels (MOX).
A. Magni +4 more
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Processing waste printed circuit boards for material recovery [PDF]
, 2007 PURPOSE We have investigated the use of pyrolysis for the processing of waste printed circuit boards (PCBs). The aim was to make the process of separating the organic, metallic, and glass fibre fractions of PCBs much easier and therefore make ...
Hall, W.J., Williams, P.T
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Analysis of Fuel Burnup and Transmutations at High Burnup of Sodium Fast Breeder Reactor
مجلة بغداد للعلوم, 2022 In this paper, the Monte Carlo N-Particle extended computer code (MCNP) were used to design a model of the European Sodium-cooled Fast Reactor. The multiplication factor, conversion factor, delayed neutrons fraction, doppler constant, control rod worth,
Nehal Mohamed +3 more
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A Suzuki Coupling Based Route to 2,2'-Bis(2-indenyl)biphenyl Derivatives [PDF]
, 2002 Because of the promising performance in olefin polymerization of 2,2'-bis(2-indenyldiyl)biphenyl zirconium dichloride, we developed a new and broadly applicable route to 2,2'-bis(2-indenyl)biphenyl derivatives.
Arts, Henricus J., +5 more
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Research and Analysis of Thermal Parameter of Million-kilowatt Sodium-cooled Fast Reactor
Yuanzineng kexue jishuThe million-kilowatt sodium-cooled fast reactor is a mature and commercially promising reactor type, playing a key role in the integrated closed sodium-cooled fast reactor nuclear energy system (integrated fast reactor).
DING Tongwei1, CHEN Wei2, WANG Wenjie3
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Research Progress in Key Thermal-hydraulic Issue of Sodium-cooled Fast Reactor
Yuanzineng kexue jishuSodium-cooled fast reactors are considered the preferred reactor type for fourth generation nuclear energy systems due to their high thermal efficiency, high fuel utilization efficiency, inherent safety, and unique advantages of achieving a closed fuel ...
YANG Hongyi1, XUE Xiuli1, , , ZHOU Zhiwei1, LIN Chao1, LI Hongrui2, GAO Xinzhao1, YU Xintai1, MA Xiao1, XIAO Yubai1, LUO Rui2
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