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Systems Analysis Development for ARIES Next Step

Systems Analysis Development for ARIES Next Step. C. E. Kessel 1 , Z. Dragojlovic 2 , and R. Raffrey 2 1 Princeton Plasma Physics Laboratory 2 University of California, San Diego ARIES Next Step Meeting, June 14-15, 2007, General Atomics. Outline. Basic systems code flow

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Systems Analysis Development for ARIES Next Step

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  1. Systems Analysis Development for ARIES Next Step C. E. Kessel1, Z. Dragojlovic2, and R. Raffrey2 1Princeton Plasma Physics Laboratory 2University of California, San Diego ARIES Next Step Meeting, June 14-15, 2007, General Atomics

  2. Outline • Basic systems code flow • Explanation of what is in the Engineering Module • Inboard thickness examples • Inboard TF coil thickness versus BT (fixed area fraction model) • Inboard shield thickness versus Nw at plasma (Laila correlation) • Example of rejecting power when qpeak exceeds critical value • Scan showing impact of radiated power fraction in divertor • Future work

  3. Systems Code Being Developed Systems analysis flow physics engineering build out/cost Inboard radial build and engineering limits Top and outboard build, and costing Plasmas that satisfy power and particle balance Scan several plasma parameters to generate large database of physics operating points Screen physics operating points thru physics filters, engineering feasibility, and engineering filters Surviving feasible operating points are built out and costed, graphical display of parameters (COE)

  4. Engineering Module: Physics Filters, Engineering Feasibility, and Engineering Filters • Example of physics filter: • PCD > Paux, reject operating point • fBS > 1.0, reject operating point • Determine plasma power and radiated power from core/mantle: • Pplas = Palpha + Paux • Prad = Pbrem + Pcycl + Pline • Calculate average and peak heat flux on FW: • QpeakFW = Prad x fpeaking / AFW • QaveFW = Prad/AFW • AFW = 2R x 2a x √(1+2)/2* • If QpeakFW > 1.0 MW/m2, reject operating point • Calculate power to divertor: • Pdiv = Pplas - Prad • Pdivrad = Pdiv x fdivrad • Poutboardcond = (Pdiv - Pdivrad) x foutboard • Pinboardcond = (Pdiv - Pdivrad) x finboard

  5. Engineering Module: Physics Filters, Engineering Feasibility, and Engineering Filters Cont’d • Qpeakdiv,out = Poutboardcond / [2(R-a/2) x fexpout x pow] • Qpeakdiv,in = Pinboardcond / [2(R-a) x fexpin x pow] • Qpeakdiv,rad,out = (Pdivrad x fdivrad,out) / [2(R-a/2) x 2 x (a/2)] • Qpeakdiv,rad,in = (Pdivrad x fdivrad,in) / [2(R-a) x 2 x (a/4)] • Qpeakout = Qpeakdiv,out + Qpeakdiv,rad,out • Qpeakin = Qpeakdiv,in + Qpeakdiv,rad,in • If Qpeakout or Qpeakin > 20 MW/m2, reject operating points • Neutron powers: • Pneut = 4 x Palpha / 5 • Pneut2 = Mblkt x Pneut • Electric Power: • Pelec = th x [Pneut2 + (Pplas - Pplasx)] x (1 - fpump - fsubs) - Paux / aux • If Qpeakout or Qpeakin > 12 MW/m2, reject power • If QpeakFW > 0.75 MW/m2, reject power • Precir = Paux / aux + th x [Pneut2 + (Pplas - Pplasx)] x (fpump - fsubs)

  6. Engineering Module: Physics Filters, Engineering Feasibility, and Engineering Filters Cont’d • Inboard Radial Build: (red signifies model available) • SOL, FW, gap1,blkt, gap2,shld,gap3, VV, gap4, TF, gap5, BC, gap6, PF • shld= 0.24 + 0.067 x ln(Nw/3.26) • TF coil: • ITF = BT x 2R / (oNTF) • RTFout = R - a - SOL - FW - gap1 -blkt - gap2 -shld -gap3 - VV - gap4 • BTmax = oNTFITF / 2RTFout • If BTmax > 21 T, reject operating point • JTFoverall = [0.9 x all - (Btmax)2 / 2o] / [all x (1/JSC +1/Jcu + (R Btmax / ) x ln(RTFoutboard / RTFinboard) - Cu / Jcu] • ATF = NTFITF / JTFoverall • RTFin = √[(RTFout) - ATF / ] • Also have a fixed area fraction model, and a stress model

  7. Engineering Module: Physics Filters, Engineering Feasibility, and Engineering Filters Cont’d • Bucking Cylinder: • RBCout = RTFin - gap5 • hBC = 1.2 x (2a) • Pressure = (RBCout / RTFave) x [(BTmax)2 / 2o] • RBCin = √[(RBCout)2 x (1 - (2 x Pressure) / BCmax))] • Also a buckling limit, not checked yet • PF coil: (center stack only) • RPFout = RBCin - gap6 • hPF = hBC •  = oRIp x (lext + (li / 2) + Cejima) • BPFmax =  / (2 x RPFout) • If BPFmax > 16 T, reject operating point • Loop over RPFin, to reach JSC < JSClim

  8. Engineering Module: Physics Filters, Engineering Feasibility, and Engineering Filters Cont’d • Examples of Engineering Filters: • 975 ≤ Pelec ≤ 1025 ---> to isolate 1000 MWe points • Paux ≤ 80 MW ---> isolate lowest auxiliary power solutions (similar to lowest Precir, but not exactly) • 0.25 ≤ (Pdivrad / Pdiv) ≤ 0.75 ---> isolate radiated power fraction to have feasible divertor design and power balance • BT < 6 T versus BT < 10 T ---> examine how being more aggressive on magnets can enlarge your operating space • ……

  9. Systems Code Test: Physics Database Intended to Include ARIES-AT Type Solutions • Physics input: (not scanned) • A = 4.0 • = 0.7 n = 0.45 T = 0.964 • = 2.1 li = 0.5 Cejim = 0.45 CD = 0.38 rCD = 0.2 Hmin = 0.5 Hmax = 4.0 Zimp1 = 4.0 fimp1 = 0.02 Zimp2 = 0.0015 fimp2 = 18.0 Tedge /T(0) = 0.0 nedge /n(0) = 0.27 • Physics input: (scanned) BT = 5.0-10.0 T N = 0.03-0.06 q95 = 3.2-4.0 n/nGr = 0.4-1.0 Q = 25-50 He*/E = 5-10 R = 4.8-7.8 m Generated 408780 physics operating points

  10. TF Coil Thickness versus BT, Using 3 Different Models

  11. Inboard Shield Thickness versus Nw at the Plasma

  12. Impact of Rejecting Power in Divertor and FW if Qpeak Exceeds a Limit We have thrown out operating points that can not produce Pelec = 1000 MW, when divertor/FW power is rejected, but we have also brought in higher Pfusion operating points with enough neutron power to compensate

  13. Examine Impact of Radiated Power Fraction in the Divertor • The plasma power is given by Palpha + Paux • Some of this power is radiated from the plasma core/mantle to the first wall, Pbrem + Pcycl + Pline • The remainder goes to the divertor • We then assume some fraction is radiated in the high density / low temperature divertor slot • What ever is not radiated is conducted along the field line to the target plate • Examine the difference in surviving operation space when fdiv, rad is 30, 60, and 90% • Use same physics database, and engineering module with divertor and FW heat rejection when the heat flux is too high, and blanket sizing from Laila’s correlation

  14. Scan of fdiv,rad Only at high radiated power fraction can we access the small major radius plasmas, and low peak heat flux in outboard divertor ITER ITER ELMy H-mode Pfusion ITER ELMy H-mode Paux

  15. Scan of fdiv,rad ITER

  16. Scan of fdiv,rad ITER ITER

  17. Scan of fdiv,rad ITER

  18. Future Work • Now that costing is available, coordinate scans with Zoran, and begin looking at technical trends and graphical presentation • Need to exercise the systems code to decide what needs to be done • Physics module • Have numerical volume, area, perimeter calculation, will incorporate and make consistent with artificial flux surfaces • Separate electron and ion power balances have been worked out, need to input Ee (or Ei) to solve equations • Have input specification for ITER H-mode and SS mode, working on ARIES-I, etc. • Multiple fusion reactions, etc, etc • Engineering Module • PF coil algorithm based on plasma boundary and coil contour • Any upgrades to TF model? • Even if blanket can only be treated by neutronics, can a model be made for VV, etc, etc

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