U.S. Fusion Road Map Study 	  D.	  Meade,	  A.	  Garofalo,	  D.	  Hill,	  C.	  Kessel,	  B.	  Lipschultz(D.	  Whyte),	  	  	  N.	  Morley,	  G.	  NavraBl,	  H.	  Neilson,	  D.	  Rasmussen,	  and	  S.	  Zinkle	  	  MagneBc	  Fusion	  Program	  Leaders	  Road	  Map	  Study	  Group	  FESAC	  Strategy	  Panel	  Public	  MeeBng	  Washingtonian	  MarrioN	  Gaithersburg,	  MD	  July	  9,	  2014	  1	  h"p://ﬁre.pppl.gov	  MagneBc	  Fusion	  Program	  Leaders	  (MFPL)	  Road	  Map	  Study	  Goal:	  	  Develop	  and	  assess	  three	  aggressive	  technically	  feasible	  paths	  for	  the	  US	  Fusion	  Program	  moAvate	  a	  commitment	  to	  DEMO	  on	  the	  Amescale	  of	  ITER	  Q	  ≈	  10	  experiments	  (nominally	  2028)	  with	  DEMO	  by	  mid-­‐century.	  
1) ITER	  directly	  to	  a	  Tokamak	  DEMO	  (possibly	  staged)	  2) ITER	  plus	  Fusion	  Nuclear	  Science	  Facility	  leading	  to	  a	  Tokamak	  DEMO	  3) ITER	  plus	  addiAonal	  faciliAes	  leading	  to	  a	  QS	  -­‐	  Stellarator	  DEMO	  Each	  of	  these	  paths	  will	  include	  major	  aspects	  of	  a	  broad	  supporAng	  research	  program.	  
Working	  Group	  Members:	  Meade	  (Chair),	  Garofalo,	  Hill,	  Kessel,	  Lipschultz/Whyte,	  Morley,	  NavraAl,	  Neilson,	  Rasmussen,	  Zinkle	  We	  have	  made	  one	  pass	  through	  the	  Road	  Map,	  this	  work	  is	  in	  Progress.	  
Status	  reports	  given	  at:	  	  APS/DPP-­‐2013,	  FPA-­‐2013,	  2nd	  IAEA	  DEMO	  Workshop,	  MIT-­‐2014,	  Fusion	  Energy	  System	  Study	  -­‐	  2014,	  Columbia	  Univ	  -­‐	  2014	  General Considerations• Road Map driven by Goal and Associated Missions- Goal is a Fusion Power Plant (FPP)- Use recent ARIES Study to define general characteristics of DEMO/FPP- Mission structure is similar to EU Fusion Road Map and 2007 FESAC Report• Strive for quantitative milestones and metrics as mileage markers- Quantitative dimensional and dimensionless Figures of Merit (FESAC 2007).
- Technical Readiness Levels- EU Road Map used TRLs for materials and technology- NAS IFE Assessment 2013 used TRLs in IFE Road Map (p.162)• Setup logic Framework for Mission milestones and Decision points• Identify facilities needed to achieve mission milestones• Detailed cost estimates are beyond scope our exercise, however must
- identify compelling near term deliverables to bootstrap funding of later steps

3	  ARIES	  Studies	  IdenBﬁed	  General	  CharacterisBcs	  	  of	  MagneBc	  Fusion	  Power	  Plants	  Compact	  Stellarator	  Advanced	  Tokamak	  ARIES-­‐ACT1	  ARIES-­‐ACT2	  ARIES-­‐CS	  6.25	  9.75	  7.75	  B(T)	  /	  B	  max-­‐coil	  (T)	  6.0/10.6	  8.75/14.4	  5.7/15.1	  βN	  / βtot	  (%)	  5.6/6.5	  2.6/1.7	  -­‐/6.4	  PFusion	  	  (MW)	  1813	  2637	  2440	  fbs	  (%)	  91	  77	  ~25	  R(m)	  <Γn>	  	  MWm-­‐2	  2.5	  1.5	  All	  steady-­‐state	  at	  1,000	  MWE	  2.6	  4	  ARIES ReferenceMajor	  Mission	  Elements	  on	  the	  Path	  to	  an	  MFE	  Power	  Plant	  	  Mission	  1.	  	  Create	  Fusion	  Power	  Source	  Mission	  2.	  	  Tame	  the	  Plasma	  Wall	  Interface	  Mission	  3.	  	  Harness	  the	  Power	  of	  Fusion	  Mission	  4.	  	  Develop	  Materials	  for	  Fusion	  Energy	  Mission	  5.	  	  Establish	  the	  Economic	  A"racAveness,	  and	  	  	  	  	  	  	  	  Environmental	  Beneﬁts	  of	  Fusion	  Energy	  	  	  	  •	  Restatement	  of	  Greenwald	  Panel	  and	  ReNeW	  themes	  •	  	  Each	  Mission	  has	  ~	  ﬁve	  sub-­‐missions	  5	  TRLs	  express	  increasing	  levels	  oIncreasingf	  integraAon	  anTRLs	  express	  ofincreasing	  levels	  of	  integraAon	  TRLs
ExpressLevels
Integration
and and	  relevance	  to	  ﬁnal	  product	  and	  can	  idenAfy	  R&D	  Gaps.	  	  	  	  	  Relevance
to Final Goal and can Identify R&D Gaps.
d	  relevance	  to	  ﬁnal	  product	  and	  can	  idenAfy	  R&D	  Gaps.	  	  	  	  	  Normally TRLs are applied to technology projects, here we are attempting toapply the concept to R&D activities – NAS IFE Report 2013 page 162, Table 4.3
Add CE, POP, POPerf, BP, DEMO

6	  

More Work Needed here
• Compare with EU, NAS IFE Rpt, FESAC Materials Rpt• Describe reqmts for each TRL with issues, milestones

7	  Milestones	  can	  be	  Deﬁned	  to	  Clarify	  TRLs	  Key:••••Now	  Now

*	  Support Facilities

A"ain	  high	  burning	  plasma	  performance	  	  Now	  	  	  	  	  	  	  TRL	  4:	  	  	  Q~1	  achieved	  in	  DT	  experiments	  in	  TFTR/JET	  &	  extended	  with	  DT	  in	  JET	  2017	  	  with	  a	  Be	  wall	  Control	  high	  performance	  burning	  plasma:	  	  Now	  	  	  	  	  	  TRL	  3:	  	  	  Q~1	  DT	  experiments	  in	  TFTR/JET	  see	  self-­‐heaAng	  	  	  	  *	  	  	  	  	  	  TRL	  4:	  	  	  DIII-­‐D	  ECH	  dominated	  ITER	  baseline	  experiments	  	  	  	  JET	  DT	  experiments	  on	  TAE	  transport	  in	  Q~1	  DT	  plasmas	  with	  Be	  walls	  Sustain	  fusion	  fuel	  mix	  and	  stable	  burn:	  	  	  	  	  	  	  	  	  TRL	  5: 	  NBI	  TriAum	  fueling	  in	  TFTR/JET	  &	  cryo	  pellet	  injecAon	  technology	  Sustain	  magne9c	  conﬁgura9on-­‐AT	  Conﬁgura9on:	  	  	  Now	  	  	  	  	  	  	  TRL	  4: 	  Bootstrap	  current	  widely	  observed;	  non-­‐inducAve	  sustained	  plasmas	  observed	  	  	  	  	  	  	  	  	  	  	  	  	  	  on	  JT-­‐60U	  &	  DIII-­‐D	  using	  NBI-­‐CD/LHCD/ECCD	  	  	  	  *	  	  	  	  	  	  TRL	  5-­‐6: 	  DIII-­‐D/K-­‐STAR/JT-­‐60SA	  observaAon	  of	  ≥80%	  bootstrap	  sustained	  plasma	  	  	  	  EAST/K-­‐STAR/WEST	  observaAon	  of	  RF	  &	  bootstrap	  sustained	  SS	  plasma	  •	  	  Sustain	  magne9c	  conﬁgura9on-­‐ST	  Conﬁgura9on:	  Now	  –	  TRL	  3: 	  Bootstrap	  current	  observed	  in	  NSTX;	  CHI	  demonstrated	  non-­‐inducAve	  current	  drive	  –*	   	  TRL	  4: 	  NSTX-­‐U	  demonstrate	  non-­‐inducAve	  start-­‐up	  and	  sustainment	  extrapolable	  to	  FNSF-­‐AT	  •A"ain	  high	  burning	  plasma	  performance	  compa9ble	  with	  plasma	  exhaust:	  	  	  Now	  	  	  	  	  	  	  	  TRL	  3: 	  JET/DIII-­‐D/ASDEX-­‐U	  demonstraAon	  of	  detached	  divertor	  operaAon	  	  	  	  *	  	  	  	  	  	  	  TRL	  4: 	  JET/DIII-­‐D/K-­‐STAR	  demonstraAon	  of	  detached	  divertor	  in	  SS	  AT	  ITER	  like	  plasma	  	  	  •	  	  	  	  	  	  	  TRL	  4:	  	  	  	  NSTX-­‐U	  demonstraAon	  of	  advanced	  divertor	  operaAon	  in	  FNSF-­‐ST	  like	  plasma	  	  	  	  	  *	  	  	  	  	  	  TRL	  5: 	  Test	  stand	  validaAon	  of	  long	  lifeAme	  divertor	  PMI	  material	  8	  s)	  Mission	  1:	  Create	  Fusion	  Power	  Source	  Gap	  ITER	  FNSF	  DEMO	  1000s	  Add	  projected	  JT60-­‐SA,	  EAST,	  KSTAR,	  W7-­‐X,	  Fusion	  Plasma	  Sustainment	  Time	  (sec)	  FESAC	  IC	  Version,	  ModiﬁcaAon	  of	  Kikuchi	  ﬁ9	  gure	  Compare with EU assessment esp. DTT
Road Map Annex 2, p.19

10	  Mission	  2:	  	  Tame	  the	  Plasma	  Material	  Interface	  Gap	  PFC	  Thermal	  Eq	  ITER	  PFC	  ParAcle	  Eq	  Pheat/S	  PFC	  	  Erosion/RedeposiAon	  (MWm-­‐2)	  Pdiv/Adiv	  ≤	  10	  MWm-­‐2	  ModiﬁcaAon	  of	  FESAC-­‐IC	  ﬁg.	  

•	  Pheat	  =	  plasma	  hea-ng	  power	  •	  	  eﬀect	  of	  core	  radia-on	  •	  Update	  points-­‐	  W7,EAST,West	  •	  Label	  all	  points-­‐achieved/planned	  •	  role	  of	  linear	  machines	  11	  12	  Blanket Facilities to Reduce Gaps for all Pathways
2000

2010

2020

2030

Fusion	  Power	  Conversion	  2040

Facilities described in FESAC
Materials &Technology Rpt 2012

EU,	  CN,	  Blanket	  Test	  FaciliAes	  BT3F	  Blanket Thermomechanics and Thermofluid Test Facility (BT3F)

TriAum	  Breeding	  EU,	  JA,	  CN	  BTEF	  Bred Tritium Unit Cell and Extraction Test Facility (BTEF)

Reliability/Maintainabiity	  EU,	  CN,	  Remote	  Handling	  FaciliAes	  RHDF	  Fuel	  and	  Exhaust	  Processing	  TSTA,	  TFTR,	  JET,	  	  …….	  

Remote Handling Development Facility (RHDF)

ITER	  TBM	  Tritum	  Test-­‐STAR,	  	  	  	  	  	  	  	  	  	  	  	  	  	  	  	  	  	  	  	  	  	  	  	  	  	  FCDF	  	  Fuel Cycle Development Facility (FCDF)

EU	  DEMO	  CDA	  EDA	  FNSF	  ConstrucAon	  Operate	  13	  14	  Mission	  4:	  Create	  Materials	  for	  Fusion	  Power	  Gap	  Reduced	  AcAvaAon	  FerriAc	  Steel	  9Cr	  RAFM	  FNSF Goal

ModiﬁcaAon	  of	  Zinkle	  ﬁg.	  Materials Facilities to Reduce Gaps for all Pathways
2000

2010

2020

2030

2040

Fission	  Neutron	  Tests	  SpallaAon	  –	  SINQ,	  SNS,	  MTS	  Integrated	  Fission/SpallaAon	  Test	  Neutron	  Materials	  SimulaAons	  EVEDA	  US	  Join	  EVEDA?	  

IFMIF	  US	  Join	  IFMIF?	  

ITER	  TBM	  US	  Join	  ITER	  TBM?	  
Design	  EU	  DEMO	  CDA	  Const	  EDA	  FNSF	  ConstrucAon	  Operate	  16	  17	  Mission /TRL Milestones can be used to Inform Decisions
2000

Create	  Fusion	  Power	  Source	  Tame	  Plasma	  Wall	  Interface	  Harness	  Fusion	  Power	  Materials	  for	  	  Fusion	  Power	  2010
ITER
Basis

2020
FNSF FNSF
CDA EDA

2030

FNSF
Const

DEMO DEMOCDA EDA

2040
DEMO
Const

TRL=457.5?

9TRL=457.5?

9TRL=237.5?

9TRL=237.5?

8Economic	  	  A"racAveness	  ITER
Initiate
Construction
LegendMilestone

DT
Initiate
DefineOperation
MissionFNSF
Initiate Initiate Initiate
CDA
EDA Const.

Decision Point
Goal

ITER + FNSF => AT DEMO Pathway

Gain~10 DEMO
500 MW Basis
Initiate
Operation

Phase I Phase II
Results Results DEMOOPSDEMO
Initiate Initiate
Initiate
CDA
EDA
Construction

Electricity
From18	  Fusion

FNSF(AT) Mission for ITER + FNSF => AT DEMO Pathway
Create	  Fusion	  Power	  Source	  	  •	  	  A"ain	  required	  AT	  BP	  Parameters	  (H98>1.1;	  βN>2.8;	  100%	  NI)	  	  for	  Steady-­‐state	  	  •	  	  Demonstrate	  AT	  BP	  plasma	  control	  and	  eliminaAon	  of	  plasma	  transients	  	  •	  	  Demonstrate	  fusion	  power	  stability	  and	  control	  of	  fusion	  power	  output	  	  •	  	  Verify	  and	  Validate	  BP	  scenario	  SimulaAons	  for	  DEMO–	  what	  does	  this	  mean?	  
Tame	  Plasma	  Wall	  Interface	  	  •	  	  Demonstrate	  Div	  Power	  Handling	  at	  DEMO	  Power	  DensiAes	  in	  Steady	  state	  	  •	  	  Test	  Candidate	  Divertor	  Materials	  –	  Power	  &	  ParAcle,	  reactor	  relevant	  	  •	  	  Verify	  and	  Validate	  for	  DEMO	  Harness	  Fusion	  Power	  	  •	  	  Demonstrate	  a	  closed	  fusion	  fuel	  cycle	  with	  TBR	  ~	  1	  that	  projects	  to	  TBR>1	  in	  DEMO	  	  •	  	  Validate	  Candidate	  Fusion	  Blanket	  concept	  in	  a	  fusion	  environment	  (Γn>1	  MWnm-­‐2)	  	  •	  	  Extract	  high	  grade	  heat	  and	  produce	  some	  electricity	  for	  extended	  period	  of	  Ame	  	  •	  	  Thermal	  mechanical	  tests	  of	  blanket	  modules	  in	  fusion	  enviroment,	  	  reliability	  data	  Materials	  for	  Fusion	  Power	  	  •	  	  Demonstrate	  components	  for	  ~	  20	  -­‐	  30	  dpa,	  He	  ~100-­‐300	  ppm	  	  •	  	  IniAal	  data	  of	  neutron	  eﬀects	  on	  welds,	  etc	  (Engineering	  Feasibility-­‐Finesse	  Stage	  II)	  •	  	  IniAal	  data	  component	  lifeAme,	  reliablity	  and	  replacement	  Ame	  19	  ITER + FNSF => AT DEMO Pathway(Milestones to Initiate Construction of AT FNSF)

Create	  Fusion	  Power	  Source	  	  	  •	  	  a"ain	  required	  AT	  Parameters	  (H98>1.1;	  βN>2.8;	  100%	  NI)	  	  for	  4	  τcr	  	  •	  	  demonstrate	  plasma	  control	  (≤	  1	  unmiAgated	  disrupAon	  per	  year)	  	  •	  	  V&V	  AT	  Plasma	  SimulaAons	  for	  FNSF	  operaAng	  scenario,	  	  Tame	  Plasma	  Wall	  Interface	  	  •	  	  Demonstrate	  Exhaust	  Power	  Handling:	  P/S	  =1-­‐2	  MWm-­‐2	  with	  Pdiv/Adiv<10	  MWm-­‐2,	  1	  week	  	  •	  	  Qualify	  Candidate	  Divertor	  Materials	  –	  Temp,	  TretenAon,	  erosion	  life,	  neutron	  eﬀects	  	  •	  	  V&V	  PMI	  SimulaAons	  for	  FNSF	  exhaust	  power	  handling	  integrated	  with	  core	  plasma	  Harness	  Fusion	  Power	  	  	  •	  	  Leading	  Candidate	  blanket	  concept	  idenAﬁed	  and	  R&D	  taken	  to	  TRL~5	  	  	  	  •	  	  Qualify	  TriAum	  Handling	  Plan	  	  	  •	  	  Qualify	  Remote	  Maintenance	  Scheme	  Materials	  for	  Fusion	  Power	  	  •	  	  IdenAfy	  blanket	  structural	  material	  and	  	  qualify	  up	  to	  25	  dpa	  	  •	  	  Demonstrate	  viable	  materials	  and	  technology	  for	  conAnuous	  triAum	  extracAon	  from	  fusion	  blankets	  	  •	  Establish	  Economic	  A"racAveness	  and	  Enironmental	  Beneﬁts	  of	  fusion	  	  •	  	  Preliminary	  Safety	  Analysis	  approved	  Need	  similar	  for	  ST	  FNSF	   20	  	  •	  	  Environmental	  Impact	  Statement	  approved	  	  	  Is	  Pilot	  Plant	  FNSF	  a	  DEMO?	  	  Milestones and Major Decisions in the QS-Stell Pathway
2000

2010

Create	  Fusion	  Power	  Source	  Tame	  Plasma	  Wall	  Interface	  2020

QS Stellarator
Basis

Stell-NS
Basis

Confirm
Basis

ITER
Basis

QS Stellarator
Basis

Stell-NS
Basis

Confirm
Basis

Stell-NS
Basis

Confirm
Basis

Stell-NS
Basis

Confirm
Basis

Stell-NS
Basis

Gain ~10 Confirm
Basis
500 MW

Stell-NS
Basis

Confirm
BasisMaterials	  for	  	  Fusion	  Power	  Initiate
Operation
unlinked

Initiate
Construction

Legend2040

ITER
BasisHarness	  Fusion	  Power	  W7-X
Initiate
Construction
1996
ITER

2030

QS Stell Exp
Initiate

Milestone
Stell-NS = Stellarator Next Step
Decision Point NS Mission Options:
Burning Plasma (BP) or
Goal
Pilot Plant (PP)

Decide NS
Mission:BP or PP

Confirm
Basis

Stell-NS
Initiate
DesignInitiate
Construction

Initiate21	  Operation

Major Decisions for US Magnetic Fusion Program Road Map
20002010

2020

C-­‐Mod,	  DIII-­‐D,	  ASDEX-­‐U,	  JET	  NSTX-­‐U,	  MAST-­‐U	  2030

2040

AT	  or	  ST	  for	  FNSF?	  

EAST,	  KSTAR	  WEST	  Adv	  Tokamak	  	  Pathway	  	  	  	  JT60-­‐SA	  AT	  OK	  for	  Demo	  Basis?	  

ITER	  JET	  ITER	  AT	  or	  ST	  FNSF	  PMI	  FaciliAes	  Blanket	  FaciliAes	  Materials	  FaciliAes	  OK	  for	  FNSF?	  

QS	  Stellarator	  Pathway	  QSSE	  W7-­‐X	  LHD	  Stellarator	  Base	  Program	  DEMO	  OK	  for	  Demo	  Basis?	  

Stellarator	  NS	  QSS	  	  OK	  for	  BP	  or	  PP	  Basis?	  

DT	  Non-­‐DT	   22	  Concluding	  Remarks	  •	  A	  10	  Year	  Strategic	  Plan	  should	  not	  be	  a	  simple	  roll	  forward,	  but	  must	  be	  based	  on,	  and	  driven	  by,	  a	  longer	  term	  vision	  i.e.	  a	  Road	  	  Map.	  
•	  	  The	  10	  Year	  Strategic	  Plan	  for	  fusion	  must	  idenAfy	  several	  compelling	  deliverables	  that	  when	  accomplished	  will	  serve	  to	  increase	  	  support	  for	  fusion	  in	  the	  US.	  	  This	  will	  also	  help	  serve	  to	  focus	  the	  acAviAes,	  and	  create	  a	  sense	  of	  urgency	  in	  the	  community.	  
•	  The	  Framework	  for	  a	  Fusion	  Road	  Map	  can	  help	  in	  idenAfying	  and	  assessing	  	  the	  criAcal	  issues,	  milestones	  and	  decision	  points.	  	  Congress/AdminstraAon	  need	  to	  be	  able	  to	  track	  progress	  through	  milestones	  and	  decision	  points.	  
•	  If	  one	  of	  the	  goals	  of	  the	  10	  Year	  Strategic	  Plan	  is	  for	  the	  U.	  S.	  to	  be	  among	  the	  world	  leaders	  in	  fusion	  –	  this	  will	  require	  a	  signiﬁcant	  increase	  in	  funding,	  to	  levels	  comparable	  to	  EU	  funding	  (	  $1.34B	  in	  2014).	  	  	  23