Work Supported by US DOE Contract

1
Work Supported by US DOE Contract No.
DE-AC02-76CHO-3073
SAMPLE CASES
EFFECTIVE BLANKET AREA
USE OF SOLVER
Minimum R0 solutions which meet criteria assuming
HHi and HHe 1.0

• Blanket area is the total plasma facing surface
  area minus the effective areas of the divertor,
  center stack, and ports for the NBI, RF, and
  Diagnostics
• AblanketApfs-(WcsAcs-WdivAdiv-WportdZport(21
  .0mNnbiCnbi))
• All midplane ports assumed to have the same
  height of at least 1.0m, or
• dZport MIN(2(?R0/A-1.5),2?R0/A/3)
• Preferred port height is 1/3 of the plasma but
  we reserve 1.5m fromtop of plasma (where outer PF
  coil will be located) to top of port for remote
  handling.
• For high energy NBI (Enbi gt 120keV) negative ion
  injection methods are required, and the current
  density achievable through the NBI duct is
  assumed limited to Jnbi40A/m2 which sets the
  number of NBI ports required

• DEMO
• R02.1m
• 100MW net electric

• Typical variable set adjusted by SOLVER
• frad, fGW, ?N, qcyl, Pfusion, ?CD, JTF, fW
• Typical constraints
• frad Pbrem/P?
• Pfusion 5P?
• ?CD   ?CDmax (T) 0.025ltTgt
• PCD  Paux
• ?N  ?Nmax
• qcyl  qcylmin
• 0.1  fBS  specified limit
• 0.1  fGW  specified limit

• CTF
• R01.0m
• 10m2 test module area
• Two cases
• 1MW/m2
• - Enbi 120keV
• 4MW/m2
• - Enbi gt 120keV (NINB)

• REACTOR
• R03.0m
• 1GW net electric

reqd for mathematically valid solution

• HH factors within limits
• TF within stress temperature limits
• Divertor first wall heat load limits
• Blanket midplane n wall loading limit
• Test module n wall loading target
• Etc.

THERMAL POWER CONVERSION

• Useful thermal power is
• fblanket fraction of surface area covered by
  blanket
• fBEM blanket energy multiplication factor
  (assumed 1.2)
• kdiv toggle used to select divertor power
  recovery or not
• If toggle is on to generate electicity, gross
  electrical power production is
• Conversion efficiency ?EC is typically assumed
  35 for conventional power conversion and 45
  for advanced power conversion cycles

NET ELECTRIC POWER

• If toggle is on for electricity production,
  operation of balance of plant is assumed to
  consume a fraction (fBOP10) of gross electric
  power production
• Otherwise the balance of plant power is assumed
  to be 20MW
• The net electric power production is
• Assume PF coils superconducting (P0)
• Conversion efficiencies
• ? TF assume 90
• ? Paux assume 35 (DEMO), 45 (REACTOR)

NET TRITIUM CALCULATIONS

• The tritium fueling rate per day is
• QT-fueling P_fusion/6.54 gm/day
• Blanket local T breeding ratio (TBR) assumed
  equal to 1.2
• The net fractional breeding ratio (FBR) is as
  follows
• FBR fblanket TBR
• The net T consumption is
• QT (1-FBR) QT-fueling

BENCHMARKING

• NSTX Shot 109070

CONCLUSIONS

• ST offers promise of relatively compact fusion
  devices
• Much work needed in engineering development of
  ST device
• single turn center post
• multi-MA TF power supply
• continuous conducting shell
• Etc.
• EXCEL SOLVER provides a surprisingly powerful
  tool for simple Systems Code studies

• CTF design points were also verified by
  Strickler via SUPERCODE
• Algorithms agree with ARIES-ST with suitable
  adjustments to input assumptions