material challenges in fusion technology

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Karim HossnyE-Mail: Hossny.K@Gmail.comMaterial Challenges in Fusion TechnologyAlexandria UniversityFaculty of EngineeringNuclear & Radiation DepartmentAssociate Prof. Mohammed HassanE-Mail:

6/19/20141Team MembersTeam Leader: Karim HossnyE-Mail: Hossny.K@Gmail.comPhone no: +2 0106 93 80 868Team Members:Abd El-Rahman MagdiAkram SaidFaragRemon Samir6/19/2014Material Challenges in Fusion Technology22ContentsIntroduction for Fusion Technology.Materials for Tokamak.ITER.TBMs Materials.Li-Self Cooled TBM.Dual Coolant TBM.MHD Coating.MHD Coating Requirements.

6/19/2014Material Challenges in Fusion Technology33Introduction to Fusion

Material Challenges in Fusion Technology46/19/2014Different Fusion Fuel Scenarios4Introduction to Fusion (Contd)Material Challenges in Fusion Technology5

Vacuum Pumping DuctDiverter PlatesFW/BlanketVacuum VesselShieldToroidal Field Coil6/19/2014Magnetic Confinement Fusion Reactor5Introduction to Fusion (Contd)Material Challenges in Fusion Technology6

Bottom Blanket ModuleBottom Access Flange (Non-Breeding)First WallLaser BeamShieldBlanket Support StudFirst WallUpper Access Flange (Non-Breeding)Upper Blanket ModuleChamber Support Column6/19/2014Inertial Confinement Fusion Reactor6Materials for TokamakMaterial Challenges in Fusion Technology76/19/2014

Materials Arrangement in a Tokamak7PlasmaOutboardTopBottomInboardMaterials for Tokamak (First Wall)Table 1 Materials for the First Wall of a TokamakFirst Wall Plasma FacingLow Z-Be, C-C composites high sputtering but less quenching.High Z-W, Mo based alloys low sputtering but high quenching.First Wall Heat SinkCu-Cr-Zr alloyCopper alloys dispersion strengthened by Alumina.First Wall StructuralSteelsVanadium alloys.SiC-fiber/SiC composites.6/19/2014Material Challenges in Fusion Technology88ITER6/19/2014Material Challenges in Fusion Technology9ITER is the first magnetic confinement fusion experimental reactor, designed to test material in the true fusion environment in order to make sure of its capability for future commercial fusion reactors.For testing such materials there must be testing modules compatible with the testing port in ITER.9ITER (Contd)6/19/2014Material Challenges in Fusion Technology10Testing modules mainly are designed to test Tritium Breeding in addition to some effect of radiation on some structural material.USA does not have a Testing module to be tested in ITER, instead they are designing Fusion Nuclear Science Facility to test their own blankets.10Testing Blanket Modules MaterialsMaterial Challenges in Fusion Technology116/19/201411Testing Blanket Modules Materials (Contd)Material Challenges in Fusion Technology126/19/2014

(n,2n) Cross-section of Pb-208, Jendl 612Testing Blanket Modules Materials (Contd)Material Challenges in Fusion Technology136/19/2014Absorption Cross-section of Li-6, JENDL 4

13Testing Blanket Modules Materials (Contd)Material Challenges in Fusion Technology146/19/2014Elastic, Gamma Production Cross-section of Li-7, JENDL 4

14Testing Blanket Modules Materials (Contd)Material Challenges in Fusion Technology156/19/201415Testing Blanket Modules Materials (Contd)Material Challenges in Fusion Technology166/19/201416Li-Breeder Self Cooled TBMThe common advantages of liquid Li cooled concepts originate from the characteristics of pure Li such as high thermal conductivity, high heat capacity, high Li atomic density and low tritium pressure due to its the high solubility of tritium.

6/19/2014Material Challenges in Fusion Technology1717Dual Coolant TBMThe PbLi liquid-metal enters the blanket modules at 460C and leaves at 650C to 700C. The performed MHD calculations show that the pressure drop in the PbLi channels of the blanket due to magnetic/electric resistance is small, if all walls are covered by a SiC electric insulation of 5 mm thickness. When projected for a reference tokamak power reactor design, it has the potential for a gross thermal efficiency of > 40%.

6/19/2014Material Challenges in Fusion Technology1818MHD CoatingMHD pressure drop and MHD flow control are critical and common issues for liquid metal self-cooled blanket concept.For self-cooled blanket concepts, MHD insulators will be needed to reduce the MHD pressure drop with a reduction factor in the range of 10 to 100.

6/19/2014Material Challenges in Fusion Technology1919MHD Coating RequirementsHigh electrical resistivity.Chemical stability with lithium.Ability of coating complex channel configurations.Irradiation resistivity.Self-healing of any defects occurring.

6/19/2014Material Challenges in Fusion Technology2020Thank YouPlease Ask6/19/2014Material Challenges in Fusion Technology21Conclusion6/19/2014Material Challenges in Fusion Technology22


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