Systems Code Refinements and Updated Information J. F. Lyon, ORNL ARIES Meeting Jan. 23, 2006

Topics Revisions and additions requested at Nov. meeting Detailed results for Reference ARE case Comparison with earlier ARIES reactor cases Impact of lower p wall and higher actual B max, bucking area and divertor area Work in progress, refinements needed

Nov. Meeting Action Items 1 Correct arithmetic total of Account 21 and check all totals -- DONE 2 Correct Systems Code to agree with general structure of previous ARIES Power Flow chart NOT REQUIRED: WAS ALREADY THAT WAY (Rene’s chart)

Systems Code Power Flows Rene’s Nov. figure same as my previous flow diagram except Alpha Module part of divertor (of unknown fraction) and unknown internal flows in divertor region were called out separately 1-f rad,div P fusion P neutron PP P ,loss Divertor Chamber wall P ions+el P rad,chamb P div 80% 20% P cond P rad,div f ,loss 1-f ,loss f rad,core 1-f rad,core f rad,div Alpha modules (in Div.) F div,peak F FW,peak X X

Nov. Meeting Action Items 3 Modify algorithms and input data to reflect the use of Gross Thermal Efficiency : DONE, ADDED TO PRINTOUTS Rene Raffray supplied new gross efficiency values and He pumping power requirements – t hermal efficiency = *wload*1.52 – He pump,blanket: P = *wload*1.52 – He pump,divertor: P = 28 MW – balance of plant: 2% of gross electric power

Nov. Meeting Action Items (cont.) 4 Revise cost modeling (Account 22.2) to account for dual coolant heat transfer and transport including heat exchangers (partially Nb) and Brayton turbines –Cost2221 is primary (LiPb) coolant system Cost2221= 234.*((pthh*fLiPbcool/3500.) (pthh*fHecool/3500.) 0.55 ) *pthh*fLiPbcool –Cost2223 is secondary (He) coolant system Cost2223 = 75.*(pthh/3500.) 0.55 ) 5 Change data input for Primary Structure to reflect gravity supports (Account ) -- DONE – Cost2215 = corevol*0.184* –3 *0.95*25. *finflat/1.6348*0.94

Nov. Meeting Action Items (cont.) 6 Include coil structure (strongback and inter-coil tube) in Coil Volume and Cost -- WAS ALREADY THERE 7 Recheck Replaceable FWBS and divertor Annual cost -- ON MY LIST 8 Cost for Impurity Control is too low - $7M should be more like $55M -- WAS OK?; need good algorithm – Laila: It’s 14 M$ for ARIES-RS, 4 M$ for ARIES-AT, and 12 M$ for SPPS, so 7 M$ is not too far off

9 Other issues in Laila’s presentation a. Increase shield volume by 10% to account for penetration and local shields -- DONE b. Move “Heat Rejection System” out of Account 23 and list as separate Account CALLED 27 FOR NOW, IS 23.3 IN ARIES SYSTEM CODE – Cost27 = finflat*(pthh-pet)*37.546/2300.*1.02 c. Fix “Reactor Building” Account WAS OK, USE UNTIL BETTER ALGORITHM – Cost212 = 47.16*(Vrb/80000.) 0.62 *0.9*finflat – Vrb = 4.*(r0+rs+9.) 2 *(3.*rs) – rs = r0/acoil + cw + ccthback d. Include cryostat in Account – Laila’s flat steel cylinder used with R = 16 m, h = 18 m, 8-cm thickness, $38.9/kg

Nov. Meeting Action Items (cont.) 10 Use ARIES-AT unit cost for WC (65 $/kg) instead of Les’ value (24.4 $/kg) -- DONE 11 Add placeholder for divertor cost -- NOT REQUIRED, WAS ALREADY THERE

Nov. Meeting Action Items (cont.) 12 Do not accept design changes until after code revisions -- IN PROGRESS 13 After revisions, correct coil structure modeling in the code should be based upon the then-current design basis -- USING XUEREN’S TWO APPROACHES, THICKNESSES BELOW SCALED BY B 2 R 2 – base approach -- outer ~2/3 of shell: coil strongback 65 cm, intercoil structure 35 cm; inner ~1/3 of shell: bucking surface 85 cm – alternate approach -- coil strongback 65 cm, inter- coil structure 35 cm, no additional bucking surface – will modify if further results from Xueren

Effect of Bucking Surface on Parameters Consequences for cryostat design if separate bucking surface?

System Code Convergence VARIABLES selected for iteration and ranges major radius 5.0 to 20.0 m; field on axis 3.0 to 10.0 T ion density 1.0 to m –3 ; ion temperature 1.0 to 50.0 keV half coil depth 0.01 to 5.0 m; calculated H-ISS to 9.0 CONSTRAINTS value target ignition margin electric power (GW) volume averaged beta (%) mag field at coil (T) < max neut wall load (MW/m 2 ) 5.00 < 5.00 average/maximum density < 1.0 radial build margin A  d min /R 1.00 < 1.0 confinement mult. H-ISS < 2.00 maintenance port width (m) > 2.00 j coil /j max (B max ) 1.00 < 1.0 convergence to a solution where all constraints are satisfied is still an art common problem for multi-dimensional nonlinear constrained optimizers Reference parameters: B max multiplier = 1.25, bucking surface ~1/3 of shell, divertor 10% of wall area

Summary for Reference ARE Case MHHOPTNEW code NCSX-1 case (KZD) modified LiPb/FS/He H2O-cooled internal vacuum vessel with SiC inserts and tapered blanket inflation factor 2004 year following CONSTRAINTS were selected: ignition = 1 target 1.00 max. volume averaged beta 0.05 sufficient radial build max. neutron wall load 5.00 maximum density = 2 x nSudo Electric Power (GW) 1.00 max. confinement multiplier 2.00 min. port width 2.0 jcoil/jmax < 1 VARIABLES selected for iteration major radius field on axis ion density ion temperature coil width confinement multiplier FIGURE OF MERIT Cost of Electricity (2004 $) FINAL VALUES OF CONSTRAINTS: ignition margin 1.00 volume averaged beta (%) 5.00 radial build margin 1.00 max. neutron wall load (MW/m 2 ) 5.00 average/maximum density 0.70 Electric Power (GW) 1.00 ratio of tauE to conf. multiplier 1.66 maintenance port width (m) 3.72 jcoil/jmax 1.00 FINAL DESIGN major radius (m) 7.06 field on axis (T) 5.93 volume avg. density (10 20 m –3 ) 3.11 density averaged temp (keV) 7.16 coil dimensions (m x m) 0.22 x 0.68 current density (MA/m 2 ) 86.9

Typical Systems Code Summary Plasma Parameters central ion temp (keV) central ion density (10 20 m –3 ) 6.76 central elec. density (10 20 m –3 ) 7.03 fraction fuel to electrons 0.93 confinement time, taue (sec) 0.79 stored plasma energy (MJ) 352 volume averaged beta (%) 5.00 beta star (%) 8.21 fraction carbon impurity 0 fraction iron impurity % fraction helium 3.66 % Z effective 1.11 Mass Summary total nuclear island (tonnes) 12,343 Power Balance net electric power (MW) 1000 gross electric power (MW) fusion power (MW) thermal power (MW)  heating power (MW) power in neutrons (MW) radiated power (MW) fuel bremsstrahlung (MW) iron radiation (MW) 33.4 synchrotron radiation (MW) 1.3 conduction power (MW) fusion power to plasma (MW) fraction alpha power lost 10.0 % radiated power fraction 37.9 % max neut wall flux (MW/m 2 ) 5.00 peak thermal flux (MW/m 2 ) 0.72 ave. divertor flux (MW/m 2 ) 5.41

Power Flows for ARE Case P fusion P neutron PP P ,loss Divertor Chamber wall P ions+el P rad,chamb P div f ,loss 1-f ,loss f rad,core 1-f rad,core P thermal P elec,gross P electric P pumps, BOP

Component Cost Summary (2004$) total mod coil + str cost mod coil SC cost mod coil winding cost coil structure cost strongback inter-coil shell bucking surface total blanket, first/back wall first wall cost 6.37 front full blanket cost front blanket back wall cost second blanket cost 0.00 transition blanket cost 2.84 total vacuum vessel cost full blanket vac vessel cost shield-only vac vessel cost 2.31 transition vac vessel cost 5.13 primary structure cost shield cost and back wall ferritic steel shield cost st shield-only WC shield cost 7.04 shield-only back wall cost nd shield-only WC shield cost st transition WC shield cost 5.94 trans shield back wall cost nd transition WC shield cost penetration shield cost cost of manifolds full manifold cost transition manifold cost 5.18 total nuclear island cost cost of LiPb in core nuclear island + core LiPb

Component Mass Summary (tonnes) total modular coil mass conductor mass coil structure mass strongback inter-coil shell bucking surface total blanket, first, back wall first wall mass front full blanket mass front blanket back wall second blanket mass 0.00 transition blanket mass total vacuum vessel mass full blanket vac vessel mass shield-only vac vessel mass transition vac vessel mass primary structure mass shield mass and back wall ferritic steel shield mass st shield-only WC shield mas shield-only back wall mass nd shield-only WC shield mas st transition WC shield mass trans shield back wall mass nd transition WC shield mass penetration shield mass mass of manifolds full manifold mass transition manifold mass total nuclear island 12, mass of LiPb in core nuclear island + core LiPb 15,499.26

Component Volumes Summary (m 3 ) total modular coil volume conductor volume coil structure volume strongback inter-coil shell bucking surface total FW, blanket, BW volume first wall volume front full blanket volume front blanket back wall vol second blanket volume transition blanket volume total vacuum vessel volume full blanket vac vessel vol shield-only vac vessel vol transition vac vessel vol primary structure volume total shield + back wall volume ferritic steel shield volume st shield-only WC shield vol shield-only back wall volume nd shield-only WC shield vol st transition WC shield vol trans shield back wall vol nd transition WC shield vol penetration shield volume volume of manifolds full manifold volume transition manifold volume volume of nuclear island volume of LiPb in core r mid (m) in blue

Typical Cost Summary (2004 $) COST SUMMARY (M$) % of 99 % of Land Structure Bl. & 1st wl Shield Magnets Supp. Heating Primary Str Reactor Cryostat Power Supply Impurity Cont Direct En. Conv ECH breakdown Total Heat transport Reactor Plant Eq Turbine Plant Eq Electric Plant Eq Misc. Plant Eq Special Material Heat Rejection

Cost Element Breakdown COST COMPONENTS in 2004 year M$ Cost 20 (Land) = constant Cost 21.1 (site improvements) = constant Cost 21.2 (reactor building) = V reactor building 0.62 Cost 21.3 (turbine building) = (  th P th ) constant Cost 21.4 (cooling system) = (  th P th ) 0.3 Cost 21.5 (PS building) = constant Cost 21.6 (misc. buildings) = constant Cost 21.7 (vent. stack) = constant Cost 21 (Structure) = P th = P n x gloem + P 

Cost Element Breakdown Cost (FW) Cost (BL + BW) Cost (Bl/BW & 1st wl.) % Cost (Sh/BW/man) % Cost mod coils Cost VF coils Cost divertor Cost mod coil struct Cost (coils + str) % Cost (Heating) constant 20 MW Cost (Primary Str.) core volume Cost (Vac. Sys.) cryostat Cost (Power Sup.) constant Cost (Imp. Control) Cost (Dir. Ener. Conv. 0 Cost (ECH) = 0 Cost 22.1 (Core) =

Cost Element Breakdown Cost prim. coolant P th 0.55 Cost interm. coolant Cost sec. coolant P th 0.55 Cost 22.2 (Heat transport) Cost 22.3 aux. cooling P th Cost 22.4 rad. waste P th Cost fuel injection constant Cost fuel processing constant Cost fuel storage constant Cost atm T recover constant Cost H2O T recover constant Cost BL T recover constant Cost 22.5 fuel handling constant Cost 22.6 other plant equip P th Cost 22.7 I&C constant Cost 22 (Reactor Plant) (inc. 2% spare parts)

Cost Element Breakdown Cost 23 (Turbine Plant) (  th P th ) constant Cost 24 (Electric Plant) (  th P th ) 0.49 Cost 25 (Misc. Plant Eq.) (  th P th ) 0.59 Cost 26 (Spec. Matls.) V LiPb Cost 27 Heat Rejection P th – (  th P th )

Values for Different p wall Limits

Parameter Variation with p n,wall, max no solution above 5 MW/m 2 Increasing p wall decreases and COE until R min limit is reached

Cost Varies as 1/ no solution below 0.2 m 2 /MW

Comparison of General Plant Costs (1992 $) Only Reactor Plant Equip. contains stellarator costs

Comparison of General Plant Costs (1992 $) While the reactor equipment is the largest cost component, the costs of structure (buildings) and heat transport are also large

Comparing Costs with AT, RS & SPPS

Comparing Masses with AT, RS & SPPS

Nov. Meeting Action Items (cont.) 14 After revisions, generate parameters for advanced LiPb/SiC design with 58% thermal conversion efficiency -- ON MY LIST 15 After revisions, generate parameters for 2 PF configuration (get radial build from Laila) -- ON LIST OTHER ITEMS ON MY LIST Add cost of helium coolant Reanalyze SNS and NCSX A  -scan cases More parameter scans and sensitivity tests, n(r), T(r) Add ln(p wall /2) correction to shield thickness Modify alpha loss according to L.P. Ku’s calculations Need NbTi(Ta) case??

Refinements Needed VF or control coils not considered yet in designs, needed for startup? Effect of manifold design on  min and min Allowable maximum p n,wall Better calculation of B max / Divertor power peaking and additional costs?

Need to Check  (  ) for Vacuum Vessel to Coil Winding Surface Only done so far for no-blanket region Is there sufficient clearance for other regions? – 59 cm difference Need to revise  min or OK for NCSX cases? 28 avg. 31 avg. 19 avg. 18 –

Studied Underestimation of B max / Filamentary coil calculations underestimate B max / (by ~25%?), but relatively small effect

Allowable Divertor Peaking Factor Not Large

Summary Addressed most of the revisions and additions requested at Nov. meeting Detailed results for Reference ARE case Compared with earlier ARIES reactor cases Impact of lower p wall and higher actual B max, bucking area and divertor area Work in progress, refinements needed