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1 Neutronics Parameters for the Reference HAPL Chamber Mohamed Sawan Fusion Technology Institute University of Wisconsin, Madison, WI With contributions.

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Presentation on theme: "1 Neutronics Parameters for the Reference HAPL Chamber Mohamed Sawan Fusion Technology Institute University of Wisconsin, Madison, WI With contributions."— Presentation transcript:

1 1 Neutronics Parameters for the Reference HAPL Chamber Mohamed Sawan Fusion Technology Institute University of Wisconsin, Madison, WI With contributions from I. Sviatoslavsky (UW), A.R. Raffray (UCSD), X. Wang (UCSD) HAPL Meeting University of Rochester November 8-9, 2005

2 2 10.5 m Radius Chamber Configuration with Li Blanket

3 3  1 mm W armor on low activation ferritic steel (F82H) FW  Used target spectrum from LASNEX results (Perkins) for NRL direct-drive target  70.5% of target yield carried by neutrons with 12.4 MeV average energy  Target yield 350 MJ  5 Hz rep rate  1.75 GW fusion power  Chamber radius 10.5 m at mid-plane  Peak neutron wall loading at mid-plane is 0.89 MW/m 2 Parameters Used for Baseline Chamber Design

4 4 Schematic of Self-Cooled Li Blanket Sub-Module

5 5 Radial Build and Material Composition of Blanket and Shield/VV  Blanket thickness 60 cm  Shield/VV thickness 50 cm Homogenized material composition accounts for side walls of blanket sub-module

6 6 Design Requirements  Overall TBR >1.1 taking into account lost breeding blanket coverage (6%)  0.4% beam ports  3.6% top access flange  2% bottom access flanges  End-of-life (40 FPY) peak dpa in shield <200 dpa for shield/VV to be lifetime component  End-of-life (40 FPY) peak He production at back of shield/VV <1 He appm to allow for rewelding

7 7 Neutronics Parameters  Natural lithium is used  Local 1-D TBR is 1.18  With 94% blanket coverage the overall TBR is estimated to be 1.11  Lithium enrichment can be used to enhance TBR if needed  Local nuclear energy multiplication in blanket and shield/VV behind it is 1.15  Local nuclear energy multiplication in 1.03 m thick top and bottom flanges (62% B4C, 5% FS, 33% He) is 0.96  Overall nuclear energy multiplication is estimated to be 1.135 Tritium Breeding Nuclear Energy Multiplication

8 8 Nuclear Heating Profiles Self-cooled Li blanketShield/VV behind blanket

9 9 Plant Thermal Power for 1750 MW Fusion Power Plant Thermal Power for 1750 MW Fusion Power Total Thermal Power = 1910 MW 1627 MW removed from blanket by Li (85% of thermal power) 283 MW removed from shield/VV and top/bottom flanges by He Blanket (94% coverage) 1627 MW Shield/VV (94% coverage) 188 MW Bottom Flange (2% coverage) 34 MW Top Flange (3.6% coverage) 61 MW

10 10 Radiation Damage dpa/FPYHe appm/FPY W armor2.31.6 FS first wall9.691 Front of shield/VV1.36.5 Back of shield/VV0.0090.017 Back of flanges0.0010.004  At W/FS interface, W dpa is lower than FS dpa by a factor of 4 and W He production is lower by a factor of 57  Based on 200 dpa lifetime limit for FS structure blanket and flanges lifetime is ~20 FPY and they have to be replaced at least once during the plant lifetime  End-of-life (40 FPY) peak dpa in shield/VV is 52 dpa implying that it will be lifetime component  End-of-life (40 FPY) peak He production is 0.68 He appm at back of shield/VV and 0.16 appm at back of flanges allowing for rewelding

11 11 Impact of Increasing Rep Rate  The option of increasing the rep rate above 5 Hz was considered  TBR and energy multiplication are independent of rep rate  Damage rates and power densities scale linearly with rep rate  Lifetime of blanket and flanges decreases with increased rep rate (20 FPY for 5 Hz, 10 FPY for 10 Hz)  We have enough margin for shield/VV to be lifetime component even if rep rate is increased by a factor of 3 (52 dpa @ 5Hz, 104 dpa @ 10 Hz, 156 dpa @ 15 Hz)  Rewelding at back of flanges remains possible for higher re rates (0.16 appm @ 5 Hz, 0.32 appm @ 10 Hz)  Rewelding at back of shield/VV will not be possible with 10 Hz (1.38 appm) and ~5 cm increase in thickness will be required  Thermal power of plant increases linearly with rep rate

12 12 Summary  Overall TBR >1.1 can be achieved without breeding in the shield/VV and top and bottom flanges  Shield/VV is lifetime component with 60 cm blanket  Lifetime of blanket and top/bottom flanges is expected to be ~20 FPY  Rewelding at the back of the 50 cm He-cooled shield/VV and 103 cm thick top/bottom flanges is possible  For 1750 MW f, total thermal power is 1910 MW th with 15% of it carried by the He coolant of the shield/VV and top/bottom flanges  Nuclear requirements are still satisfied if rep rate is increased to 10 Hz except that the frequency of blanket and flange replacement is increased and the shield/VV thickness should be increased by ~5 cm to allow for rewelding at its back

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