NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 20181

Outline
H
H
H
H
H
H
H

Background : Change and Reform
Staged Approach : First Plasma to DT Operation
Building and Plant Construction
Critical Components and Systems Manufacturing
Advancement of Technology R&D Area
Technology & Engineering Breakthroughs and Spinoffs
Summary
NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 2018

2

Background : Change and Reform
Action Plan 2015: Set clear priorities & timeline for reform Reorganized and Integrated ITER Central Team (IO-CT) with
Domestic Agencies
 Clear decision processes and accountability
 Executive Project Board, Reserve Fund, Project Teams Finalized and stabilized ITER critical component design Comprehensive integrated bottom-up review of all activities,
processes and systems
 Developed an optimized resource-loaded schedule fortimely, cost-effective construction and operation throughD-T plasma. Updated the 2010 Baseline (Baseline2016).
 Developed and promoted a strong, organization-wide nuclear
project culture
NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 20183

Staged Approach : FP to DT Operation
Extensive works among IO and DAs to finalize revised baseline:
Baseline2016 Schedule and Cost (OPS & OPC)
 Schedule and resource estimates through First Plasma (2025) consistent withMembers’ budget constraints
 Adopted 4-stage approach through Deuterium-Tritium Operation (2035)
consistent with Members’ financial and technical constraints

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 20184

Assembly Milestone Schedule to First Plasma
Level	  0	  Construc�on	
  Schedule	
  to	
  First	  Plasma	
  in	
  2025	
  
2016

2017

2018

Major	  ITER	  Milestones	
  

2019

2020

2021

2022

2023

2024

2025

Cryostat	  Closed	  	  	
  Start	  Machine	
  Assembly	
  Phase	
  I	
  

1st	
  Plasma	  TF	  Coils	
  	
  	
  	
  06,09,11,	
  05,03,	
  	  	
  01,04,17,14,18	
  	
  

TF	
  Coils	
  (1.1.P1A.EU.01)	
  

	
  	
  	
  	
  TF	
  Coils	
  12,13,	
  	
  	
  	
  	
  	
  	
  08,	
  	
  	
  	
  	
  	
  	
  	
  10,02,16,	
  	
  	
  	
  	
  	
  07,	
  	
  	
  	
  15	
  

	
  	
  	
  	
  	
  ITER	  CONSTRUCTION	
  AND	
  OPERATIONS	  (00.01/00.02)	
  TF	
  Coils	
  (1.1.P1B.JA.01)	
  

	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  First	  CS	
  Module	  CSL3	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  Last	
  CS	
  Module	
  CSU3	  Central	
  Solenoid	
  (1.1.P4A-­‐4B.US.01)	
  

	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  PF	
  Coils	  	  	
  05,06,02,	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  04,	
  	
  	
  	
  01	
  	
  	
  03	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  

Poloidal	  Field	  Magnets	
  
	
  	
  	
  	
  	
  	
  	
  	
  VV	
  Sector	
  	
  	
  	
  06	
  	
  	
  	
  	
  	
  	
  01(07)	
  Vacuum	  Vessel	
  (1.5.P1A.KO)	
  Vacuum	  Vessel	
  (1.5.P1A.EU)	
  VV	
  Sector	  	
  05,04,03,	
  	
  02,	
  	
  	
  	
  	
  09	
  

Vacuum	  Vessel	
  (1.5.P1A.IO)	
  VV	
  Sector	
  	
  	
  	
  08	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  07(01) 	
  Assembly	
  Bldg	
  13	
  RFE	
  1A	
  

Bldg	
  11	
  RFE	  1B	  Stage	  1	
  Building	  Construc�on	
  (6.2.P2.EU.
05)	
  

Bldg	
  11	
  RFE1B	
  Stage	  2	  Start	
  Lower	  Cryostat	  Assembly	
  Start	  VV	  Sector	
  08	
  Sub-­‐Assembly	
  	
  

VV	
  Sector	  	
  Sub-­‐Assembly	
  Completed	
  Cryostat	  Closed	  	
  (Install	  Bioshield	
  Lid)	
  End	
  Machine	
  Assembly	
  Phase	
  	
  I	
  	
  

58	
  

Construc�on	
  (2.2.P1.IO)	
  Opera�ons	
  Start	
  Machine	
  Assembly	
  Phase	  I	
  Start	  VV	  Sectors	
  Sub-­‐
Assembly	  	
  Lower	
  Cryostat	
  Assembly	
  Completed	  	
  Start	
  Cryostat	
  
Base	
  
Installa�on	
  VV	
  Sector	
  Assembly	
  Completed	
  1st	
  Plasma	  Start	  Integrated	
  Commissioning	
  I	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  	
  

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 20185

Building & Plant Construction

11 TOKAMAK BUILDING
13 ASSEMBLY BUILDING
14 TRITIUM BUILDING
15 RF HEATING BUILDING
17 CLEANING FACILITY BUILDING
19 SEISMIC ISOLATION BASEMAT21 HOT CELL BUILDING
23 RAD WASTE BUILDING
24 PERSONNEL ACCESS CONTROL BUILDING
32 MAGNET POWER CONVERSION BUILDING 1
33 MAGNET POWER CONVERSION BUILDING 2
34 NB POWER SUPPLY BUILDING
36 MAIN ALTERNATING CURRENT DISTRIBUTION BLDG
37 NB HIGH VOLTAGE POWER SUPPLY BUILDING
38 REACTIVE POWER CONTROL BUILDING
44 45 EMERGENCY POWER SUPPLY BUILDING
46 47 MEDIUM VOLTAGE DISTRIBUTION BUILDING
49 RTE CONTROL BUILDING
51 CRYOPLANT COMPRESSOR BUILDING
52 CRYOPLANT COLDBOX BUILDING
55 PF COIL FABRICATION BUILDING
56 CRYOSTAT ASSEMBLY BUILDING
57 58 SIC GENERATOR BUILDING
59 60 IP GENERATOR BUILDING
61SITE SERVICES BUILDING
62 HOT WATER BOILERS BUILDING
67 COLD BASIN & COOLING TOWERS
68 COOLING WATER PUMP STATION
71 CONTROL BUILDING
74 DIAGNOSTICS BUILDING
75 FD & SWITCHING NETWORK RESISTOR BLDG

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 20186

Tokamak Complex Design & Construction1		Integrated Building Design2		Construction Design
3	
	

4	
	

Tritium Building B14

Execution Design &Construction

Tokamak Building B11

As-Built Design

Roof	
  
L5	
  

Diagnostic Building B74

L4	
  
L3	
  
L2	
  

*	
  Design	
  Interface	  fully	  FROZEN	
  and	
  no	
  
more	
  PCRs	  aﬀec�ng	
  Tokamak	
  Building.	
  

L1	
  
B1	
  
B2	
  
NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 20187

Status of Tokamak Complex Design & Construction
Categoriza�on	
  2	

Construc�on	
  Design	  3	

Level	  Building	
  /	
  MRR	
  Acceptance	  Reports	
  approval	
  dates	  H Level	  L3	
  H Bldg.	
  11,	
  14,	
  74:	
  	
  	
  

	
  August	
  2017	
  (last	  version)	
  H Level	  L4	
  H Bldg.	
  11,	
  14	
  :	
  

	
  August	
  2016	
  (1st	  issue)	
  H Level	  L5	
  H Bldg.	
  11,	
  14:	  	
  

	  May	  2017	
  (1st	  issue)	
  H Roof	  H Bldg.	
  11,	
  14:	  H	   Bldg.	
  74:	   	
  

	  October	
  2017	
  (1st	  issue)	
  	
  August	
  2016	
  (1st	  issue)	
  H Bldg.	
  11,	
  14,	
  74:	  	
  September	
  2017	
  (Approved	  by	  IO)	  H Bldg.	
  11,	  74:

	
  January	  2018	  H Level	  B2	
  Slab	  Execu�on	
  Design	  &	
  Construc�on	  H Level	  B2	
  Walls	
  /	
  B2M	  H Level	  B1	
  H Level	  L1	
  H Level	
  L2	
  

4	

As	
  Built	
  Design	
  H Level	  B2	
  NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 20188

Tokamak Complex

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 20189

Bioshield Concrete Works Completed

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201810

Construction-by-Area Approach (Worksites)

21

14

15

Worksite 1 (TKM Assembly)
Worksite 2
Worksite 3
Worksite 4
Worksite 5 (SSEN)
Worksite 5 (PPEN)

Worksite 1: Tokamak Main Machine,
Worksite 3: Hot Cell + Rad Waste + Control Buildings,
Worksite 5: Electrical & Power Supply Buildings,

Worksite 2: Tokamak Complex Plant + RF Bldg.(B15)
Worksite 4: Cryogenic Plant + Cooling Station

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 2018

11

CTTA (Worksite 1) & CTTC (Worksite 2)
L5
L4

❺

In-cryostat

❹

L2

❸

L1

❷
❶

Port &

L3t
Cryosta

L2 Port Cell⑤④

L1 Port Cell

B1

B1 Port Cell

B2

B2 Tokamak
Interface

Gallery

Port Cell③②

Bio-shield①
In-vessel

Cryostat(Tokamak Pit)

IO CTTC
Contracts
and EU-DA
Building
Services(TB04)
Contract
Co-activity
Area
Port Cell
Bio-shield

Gallery

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201812

Tokamak Assembly Flow (B17 - B13 - B11)

-­‐
-­‐
-­‐
-­‐

Introduc�on	
  of	
  the	  Tokamak	
  components	
  in	
  Building	
  17;	
  Prepara�on	
  and	
  sub-­‐assembly	
  of	
  the	
  sectors	
  in	
  Building	
  13;	
  Transport	
  of	
  the	
  sector	
  sub-­‐assemblies	
  via	
  2x750t	
  crane	  to	
  the	  Tokamak	
  Pit;	
  Final	
  assembly	
  of	
  the	
  components/sub-­‐assemblies	
  in	
  the	  Tokamak	
  Pit.	
  	  	
  NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201813

Learning	
  Curve	  with	
  Sectors	
  6	
  &	
  7	
  
Sub-­‐assembly	
  Sector-­‐by-­‐Sector	
  Assembly	
  (KSTAR,	
  EAST,	
  JT-­‐60SA)	
  with	  Learning	  Curve	  by	
  Sectors	
  6	
  &	
  7	
  

Tokamak	  	
  Lower	
  In-­‐pit	
  Installa�on	
  Ac�vi�es	
  Tokamak
Assembly
Hall Activ
ities
Tokamak	
  In-­‐Pit	
  Installa�on	
  Ac�vi�es	  NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201814

Tokamak Assembly Tools Design

Sector Sub-Assembly Tool (SSAT)
Sector Lifting Tool
NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201815

Sector Sub-Assembly Tool (SSAT #1)

B13 Assembly
Building

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201816

Sector Sub-Assembly Tool (SSAT #2)
RH/LH Horizontal Be
am(IB) Support Block(OB) Support Bl
ock

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201817

One-of-Kind Plant : Cryogenic SystemITER	
  variable	
  heat	  loads	
  (overall	  heat	  loads)	
  
NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201818

In-kind Procurement Manufacturing
CryostatFeeders (31)Thermal shield
Toroidal Field coils (18)
Vacuum vessel

Poloidal field coils (6)Blanket modules
Correction coils (18)Central solenoid (6)Divertor

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 2018

19

Vessel Systems in Mass Production
Cryostat, Thermal Shields,
and Vacuum Vessel Sectors & Ports

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201820

Cryostat in Mass Production
Upper Cylinder

Lid

Lower Cylinder

Base Section

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201821

Thermal Shield in Mass Production

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201822

Vacuum Vessel in Full Production
 Nuclear	
  licensing	
  as	
  an	
  ESPN	
  (First	
  In-­‐Kind	
  of	
  Fusion	
  Nuclear	
  Pressure	
  Vessel)	
   The	  ITER	  VV	
  is	
  deﬁned	
  as	
  an	
  ESPN	
  (Equipement	
  Sous	  Pression	
  Nucléaire)	
  component	
  that	  requires	
  that	  all	
  documents	
   related	
   to	
   design,	
   manufacturing,	
   installa�on,	
   and	   opera�on	
   shall	   be	
   reviewed	
   and	
   approved	
  by	
   an	
   Agreed	
   No�ﬁed	
   Body	
   (ANB)	
   on	
   behalf	
   of	
   the	   French	
   Nuclear	
   Authority	
   (Autorité	
   de	   Sûreté	
  Nucléaire	
  :	
  ASN).	
  →	
  (Originally	
  designed	
  as	
  a	
  non-­‐nuclear	
  engineering	
  (French	
  nuclear	
  regula�on	
  applied	
  a�er	
  site	  selec�on))	
   1st	
  applica�on	
  of	
  the	
  RCC-­‐MR	
  2007	
  Edi�on	
  (Code	  &	  Standard)	
   As	
   main	
   C&S,	
   we	   are	   applying	
   the	   RCC-­‐MR	
   2007	
   Edi�on	
   that	
   is	
   the	   ﬁrst	
   applica�on	
   on	
   the	   ITER	   VV	  construc�on	
  that	  cause	  a	
  few	  of	
  major	
  upda�ng	
  of	
  C&S	
  itself	
  during	
  design	
  and	  manufacturing.	
   Many	  clients	
  (Complex	
  interfaces)	
  	
   The	
   VV	
   supports	
   many	   in	
   vessel	
   systems	
   such	   as	
   Blankets,	
   Diverters,	
   Diagnos�cs,	
   In-­‐vessel	
   Coils,	
   Port	  Plugs,	
  Components	
  of	
  Hea�ng	
  and	
  Current	  Drivers,	
  Fuelling,	
  Cooling	
  Pipes,	
  and	  Assembly,	
  etc.	
  Many	  of	
  func�onal	
   and	   physical	
   interfaces	
   cause	
   long	
   discussion	
   because	
   of	
   mainly	
   diﬀerent	
   design	
   maturity	
   of	  each	
  system.	
  	
  
→	
  Main	  technical	
  challenges	
  have	  been	  resolved	
  during	
  manufacturing	
  process	
  	
  	
  
→	
  All	  9	  VV	
  sectors	
  are	
  under	  manufacturing	
  and	  the	
  ﬁrst	  sector	
  (S#6)	
  has	  been	
  achieved	
  ~77	  %	  of	
  progress	  NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201823

Status of VV Production in KO
PS2

Upper Port
Delivered	
  	
  
from	
  MDT	  (RF)	
  	
  to	
  HHI	  (KO)	
  

PS3
PS1

PS4
PS : Poloidal Segment

Lower PortVV#6-­‐PS1	
  :	
  Comple�on	
  of	
  manufacturing	
  (IC-­‐23)	
  with	  mee�ng	
  all	
  required	
  tolerance	
  Manufactured	
  	
  
by	
  HHI	  (KO)	
  

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201824

Status of VV Production in EU
Upper Port

PS2

PS3

PS1
PS4
Lower Port

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201825

Superconducting Magnets in Full
Production
TF Winding Pack, TF Structure, PF Coils,
CS Coils, and CC-Coils

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201826

Status of TF WP Production in JA

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201827

Status of TF WP Production in EU

TF06

TF WP Instrumentation Test

TF09

TF11 (arrived for insertion)

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201828

Status of TFCS Production

1) Root Gap : 0.5±0.25mm2) Misalignment of Welding Root : Within±0.3mm
3) Matching the Splice Plate Side : Within ± 1.3mm

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201829

Status of TF Insertion Process

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201830

Status of PF5 ProductionH

Two PF5 Real Double Pancakes (DPs) (DP7 and DP8) windings have been completed

PF5: 2nd DP(DP8) Winding Completed
NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201831

Status of PF6 Production
H

Five PF6 Real DPs(DP5, DP6, DP7, DP8 and DP9) windings have been completed

PF6: 2nd DP(DP8) VPI Completed

PF6: 3rd DP(DP7) VPI Under Preparation

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201832

Status of PF1 Production
H

Five PF1 Real DP windings have been completed and the 5th DP is underway

PF1: 5th DP Winding Underway

PF1: 3rd DP VPI Completed

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201833

Status of CS Coil Production

CS Module-1

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201834

In-Vessel Components, Systems in
Engineering and Production
W-Divertor, Be First Wall, Shield Blocks,
and In-Vessel Coils

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201835

Status of Blanket System
Main Functions of ITER Blanket System:
H Exhaust the majority of the plasma power
H Contribute in providing neutron shielding to superconducting coils
H Provide limiting surfaces that define the plasma boundary during
startup and shutdown

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201836

Status of Blanket FW Manufacturing

Plasma	  Exaggerated	
  shaping	  RH	
  access	  NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201837

Status of W-Divertor
Divertor Main Functions :H Minimize the helium and impurities content in the plasma
H Exhaust part of the plasma thermal power

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201838

Status of W-Divertor Manufacturing

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201839

Status of In-Vessel Coil SystemThe	
  in-­‐vessel	
  coils	
  comprise:	
  3	
  x	
  9	
  picture-­‐framed,	
  ELM	
  coils	
  (aimed	
  at	
  controlling	
  Edge	
  Localized	
  Modes)	
  and	  2	  ring,	
  VS	
  coils	
  (aimed	
  at	
  controlling	
  Ver�cal	
  Stability).	
  Upper VS CoilFeedthroughs

Feeders
ELM coils(3 per sector)

Lower VS Coil

* PDR finalized successfully.
NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201840

Status of In-Vessel Coil Conductor
 Round	  conductor	
  with	  MgO	
  ceramic	
  insula�on	
   Coils	  a�achment	
  through	
  brackets	  	
   Unit	  lengths:	
  up	
  to	
  70	
  m	
  	
  
 Weight:	
  12.4	
  kg/m	  [Dimensions in mm][ASIPP]

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201841

Status of In-Vessel Coil Engineering
2 Insulating Breaks

2 Pipes(Cooling Supply)

2 Jumper Clamps(Power Supply)

2 Bellows

IVC In-situ Joint

Joints(to feeders)

Support Structure

IVC FT & IB

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201842

Advancement of Technology R&D
Heating & Current Drive Systems,
Diagnostics, Remote Handling Systems,
and Tritium Systems

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201843

Areas of Technology R&D
R&D	
  must	  be	
  complete	
  in	
  �me	  to	
  enable	
  integra�on	
  into	  design	
  and	
  implementa�on	
  for	  ITER	
  needs	
  in	
  “Staged	
  Approach”	
  By	
  internal	
  measures,	
  >85%	
  of	
  design	
  ac�vity	
  is	
  complete	
  :	
  This	
  implies	
  major	  technology	
  R&D	  is	
  complete;	
  however,	
  some	  issues	  remain	
  and	  have	  to	
  be	
  addressed.	
  FP Diagnostics, ECH Major Diagnostics HNB &ICHTritium System
RH Tools

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201844

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201845

H&CD in the ITER Research Plan
4-­‐Stage	
  Approach:	
  1st	  Plasma:	
  
	
  H	
  
� PFPO-­‐1:	
  
	
  H	
  and	
  4He	  
� PFPO-­‐2:	
  
	
  H	
  and	
  4He	  
� FPO:	
  	
  
	
  D	
  and	
  DT	
  
�

*
ECRH	
  

ICRF	
  

NBI	
  

170	
  GHz	
  (+100-­‐110	
  GHz	
  tbc)	
  40-­‐55	
  MHz	  870	  keV	
  H0,	  1	  MeV	
  D0	
  

20	
  MW	
  	
  (+20	
  MW	
  upgrade)	
  

20	
  MW	
  	
  (+20	  MW)	
  

33	
  MW	
  	
  (+16.5	
  MW)	  High	
  fusion	
  gain,	
  ST	
  control,	
  wall	  cleaning,	
  modula�on	
  <	
  1	
  kHz	  Bulk	
  current	
  drive,	
  rota�on,	
  limited	
  modula�on	
  24	
  gyrotrons	
  (24x0.8	
  MW)	  2	  antennas	
  (2x10	  MW)	  2	  injectors	
  (2x16.5	
  MW)	  

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201846

Status of ECH PS and RF Sources
Power Supplies: First Factory Acceptance Test has been completed in Nov. 2017;
corresponding installation planned for March 2019 (B15);
Gyrotron: Four tubes already in manufacturing or under factory acceptance
RF-DA: first tube’s Factory Acceptance Test started in Oct.
2017; second under manufacturing
JA-DA: first two tube’s manufactured and first
Factory Acceptance Test planned in April 2018;
EU-DA: CW prototype being tested in
Lausanne for long pulse operation

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201847

Status of HNB and DNB Systems* Front End Components

Heating Neutral Beam Injectors
Diagnostic Neutral Beam Injector
NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201848

Neutral Beam Test Facility : SPIDER BS
Cooling	  plant	
  of	
  NBTF	  Beam	
  Dump	   Scaﬀolding	
  installed	
  	
  installed	
  SPIDER	
  Beam	  Source	  :	
  installa�on	
  phase	  AGPS	
  delivered	
  and	
  installed	
  and	
  tests	  are	
  underway	
  Plant	
  systems	
  commissioning	
  with	  CODAS	  	
  IC-30: Start of integrated commissioning – end March 2018 (@ RFX)
NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201849

Neutral Beam Test Facility : MITICA
1	
  MV	
  HV	
  Deck	
  	
  

1	
  MV	
  HV	
  PS	
  system	  Beam	
  Source:	
  in	
  procurement	  MITICA	  1MV	  Bushing:	
  demonstrated	
  1MV	
  holding	
  MITICA	  vessel	  supports	
  inside	
  bio	
  shield	  wai�ng	  for	
  vessel	  MITICA	  Vessel	
  in	
  manufacturing	  	
  installa�on	
  NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201850

Status of ICH SystemRF	  SOURCES	  (Building	  15)	  	
  HV	
  POWER	  SUPPLIES	  (Building	  15)	
  -TRANSMISSION	  LINES	
  +	
  MATCHING	
  SYSTEM	  (Building	  11-­‐13-­‐15-­‐21)	
  ANTENNAS	  (Building	  11)	  Antennas: EU DA, “Build to print”, IO for the design
TL & MS: US DA, at functional specs
RF Sources : IN DA, at functional specs
HVPS: IN DA, at functional specs (44%), + IO (56%)
NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 2018

51

Status of Diagnostic SystemH

50 different diagnostics identified for different measurement roles

H

Just over 100 sub-projects (in PBS55) in all

PBS55 - Diagnostics
A- Magnetics systems
B- Neutrons systems
C- Optical systems
D- Bolometry systems
E- Spectroscopy systems
F- Microwave systems
G- Operational systems

PBS55-Engineering of:
Q- Equatorial Ports
U- Upper Ports
L- Lower ports
NW- Windows
NE- Electrical Services
PBS57- IVVSPBS58- PPTF

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201852

Challenges of Diagnostic System
H
H
H
H
H

Nuclear environment means we need to mitigate transmutation, radiation damage andthermo-electric effects
Target: zero maintenance (in practice very difficult)
Quality requirements are high, in particular for assembly to the nuclear pressure vessel andvacuum vessel feedthroughs
Many interfaces (machine-diagnostics, diagnostics-diagnostics)
Engineering (remote handling capability, neutron shielding, weight)

H How are we meeting these?
––––

Staged design, fabrication and installation approach
Joint experiments through dedicated International Tokamak Physics Activity Diagnostic Working
Group
Dedicated R&D and development in the ITER IO-DA Teams
Modular design and standardization
NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201853

Ports for Diagnostic System

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 2018

54

ITER Fuel Cycle : Tritium System

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201855

Status of Fuel Cycle
H

Fuel cycle has unprecedented throughput
requirements––

H

Vacuum pumping––

H

Design and safety analysis has advanced
H Some equipment is already installed, most systems arein preliminary/final design
High confidence that systems will work, primary questions
relate to number of shots per day that can be supported
First torus cryopump manufacturing, testing and delivery
completed
High-throughput, tritium compatible roughing pumpsuccessfully tested

Receipt	
  of	
  Torus	
  Cryopump	
  Gaseous detritiation system––

Verification testing for new, high capacity scrubber column
technology completed
Recently completed resolution of all major design issues

Tokamak	
  Complex	  Detri�a�on	
  System	  NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201856

First Torus/Cryostat Cryo-pump Fabrication

Cryo-pump Flange

Cryo-pump inlet valve alignment

Assembly of charcoal coatedpanelsCryo-pump casing
preparation for ebeam welding

Completed Cryo-pump
Thermal Shield Assembly August 2017
NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201857

Advanced Robotics and Remote Handling

Due to the massive size of the ITER Tokamak components, as well as theintense neutron flux that will occur during operations, the ITER machine
has required the development of cutting-edge robotics and remotehandling tools, which will be used in both the assembly and operational
phases.

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 2018

58

Du
at

Remote Handling Technology Development
Blanket	
  Remote	  Handling	
  (Japan)	
  Overview	
  of	
  
the	
  ITER	
  Blanket	
  RH	
  System	  Divertor	
  Remote	  Handling	
  (EU)	
  toroidial moverradial mover

Overview	
  of	
  the	  ITER	
  divertor	  remote	  handling	
  process	  transfer cask

* Strong Collaboration (VR, AR, HMI…) with RACE & Industries
Blanket	  module	  handling	
  trials	  using	  the	
  prototype	
  In-­‐Vessel	
  Transporter	
  (IVT)	
  hosted	  by	
  the	  Japanese	  Domes�c	
  Agency	
  in	
  Naka,	  Japan.	
  Divertor	
  casse�e	
  handling	
  trials	
  in	
  
the	
  ITER	  Divertor	  Test	
  Pla�orm	
  created	  by	
  the	
  European	  Domes�c	
  Agency	
  in	
  Tampere,	  Finland.	
  NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201859

Technology & Engineering
Breakthroughs and Spinoffs

NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201860

Multinational SuccessH

The single largest
superconductor procurement inindustrial history is completed :An eight-year campaign to produce
the superconductors for ITER’s
powerful magnet systems

H

Six ITER Members—China,
Europe, Japan, Korea, Russia andthe United States—have been
responsible for the production of
200 kilometres (2,800 metrictons) of cable-in-conduit
conductors, worth an estimatedEUR 610 million.
NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 2018

61

ITER Technologies are being developed, demonstrated, aredocumented, and will be available for the Members’ Fusion Programs

Considerable	
  technical	
  breakthroughs	
  and	
  spin-­‐oﬀs	
  from	  the	  ITER	  Organiza�on	
  and	  Domes�c	
  Agencies	
  ac�vi�es	
  can	  be	
  observed	
  (such	
  as	
  the	  increase	
  in	
  industrial	
  capacity	
  for	  the	
  produc�on	
  of	
  superconduc�ng	
  material).	
  The	  ITER	  Organiza�on	
  and	
  Domes�c	
  Agencies	
  
are	
  in	
  the	
  process	
  of	
  iden�fying	
  all	  the	
  intellectual	
  property	
  related	
  to	
  these	  ac�vi�es.	
  	
  NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201862

Summary
ITER focuses on the study of burning plasmas, both medium-pulse (400 s) andlong-pulse (>1000 s): enabling scientific research on the next step of fusion
science and addressing the risks related to the self-heated plasma state.
H
H
H

H

Schedule Optimization of Tokamak Assembly and Tokamak Complex Installation
with “under-pinned Critical Deliveries” showed that First Plasma in 2025
% Complete for FP installed Capital Item Components by end of December :51.5% complete including IO assembly and installation
Technologies for ITER have been developed and are in production (for First
Plasma) and nearing production (for Post-First Plasma), consistent with theneeds of the “Staged Approach”“Staged Approach” constitutes a prudent approach to investment protection
and risk management : building on the successful demonstration of the previous
stages till DT Operation
NAS Committee on Strategic Plan for US Burning Plasma Research, 1~2 Feb. 201863