Korean Contributions to ITER

Summary

This presentation provides a detailed overview of South Korea’s contributions to the ITER project through the Korea Domestic Agency (KODA) under the National Fusion Research Institute. It outlines Korea’s procurement packages—including Toroidal Field conductors, vacuum vessel sectors and ports, thermal shields, blanket shield blocks, assembly tooling, power supply converters, tritium storage, diagnostics, and test blanket modules—and highlights the technical achievements, manufacturing progress, and strategic linkage to the development of K-DEMO fusion power technology.

Page 1 - Korean Contributions to ITER

Korean Contributions to ITER

Hyeon Gon Lee ITER Korea, National Fusion Research Institute

10th ITER International School 21 January ~ 25 January 2019, KAIST, Daejeon, Republic of Korea IIS-2019 NFRI | KOREA DOMESTIC AGENCY | ITER

Page 2 - Contents

Contents

1. Overview of KO ITER Project
2. Activities of KODA Procurement
3. Summary

IIS 2019, 21 ~ 25 Jan 2019, KAIST, Daejeon, Korea (Page 2)

Page 3 - ITER Project

ITER Project

• ITER is on the way to commercial fusion reactor and it will demonstrate the feasibility and integration of science and technologies, and safety features for a fusion reactor;
• The self-sustained D-T burning plasma in ITER will generate 500 MW which is 10 times more power than it receives;
• ITER enterprise will create a new collaborative culture and standard solving energy and environmental problems and contributing to the world peace;
• All of the intellectual properties obtained belongs equally to all seven Members.

Who manufactures what? In-Kind Contribution:

• Feeders (31): China
• Toroidal Field Coils (18): EU, Japan, Korea, Russia, USA
• Poloidal Field Coils (6): China, EU, Russia
• Correction Coils (18): China
• Central Solenoid (6): USA, Japan
• Divertor: EU, Russia, Japan
• Blanket: China, EU, Korea, Russia, USA
• Vacuum Vessel: EU, Korea, Russia, India
• Thermal Shield: Korea
• Cryostat: India

Tokamak Parameters: R=6.2 m, a=2.0 m, Ip=15 MA, Bt=5.3 T, m=23,000 tons, (H) 29.0 m x (D) 28.6 m

ITER Organization & Seven Domestic Agencies: The 7 ITER Members make in-cash and in-kind contributions to the ITER Project. They have established Domestic Agencies (US, CN, EU, IN, JA, KO, RF -> ITER Project IO).

Page 4 - Technical Challenges of ITER Construction

Technical Challenges of ITER Construction

• Tokamak Complex Systems (First-of-a-kind Fusion Reactor Plant) [Illustrations and 3D architectural/engineering cutaways of the ITER Tokamak Complex and internal plant infrastructure]

Page 5 - Fusion Research and ITER Project

Fusion Research and ITER Project

• 20th Century: US-EU-RF-JA lead fusion studies; As a result, the fusion research reached on the final demonstration to assess the scientific and technological feasibility of fusion energy realization.

• ITER Project: International research project in participation of world leading scientists & engineers

Historical evolution diagram (K. Lackner): From early tokamaks (1960s–1990s: T3, T10, PLT, ASDEX, TFTR, JET, JT-60, Tore Supra, DIII-D, Alcator C-Mod, KSTAR, EAST, SST1) towards ITER, DEMO, and commercial REACTOR.

Page 6 - Brief History of ITER Project in Korea

Brief History of ITER Project in Korea

• June 2003: Join to the ITER Project

• November 2006: Signed “ITER Joint Implementation Agreement (JIA)”

• April 2007: “ITER JIA” Ratified by the KO National Assembly

• September 2007: Established the “Korea Domestic Agency (KO-DA)” under the NFRI

• May 2008: Signed the first PA for TF Conductors

• November 2014: First delivery of the TF Conductors was successfully accomplished.

• June 2017: Delivery of the SSAT-1 was accomplished (IC Milestone).

• The ITER Korea is performing all activities with respect to the Korean ITER project with full responsibilities as the Domestic Agency of the Republic of Korea.

• Its main role and activities are as follows:

  • Management of KO procurement activities
  • Delivery of the KO procurement packages with quality
  • Dispatch of KO experts to IO
  • Collaboration and coordination with IO & other DAs

Page 7 - ITER Design and Components

ITER Design and Components

Parameters: R=6.2 m, a=2.0 m, Ip=15 MA, Bt=5.3 T, m=23,000 tons, (H) 29.0 m x (D) 28.6 m

Key Components:

• Central Solenoid Coil: Nb3Sn, 6 Modules
• Poloidal Field Coil: NbTi, 6 Coils
• Toroidal Field Coil: Nb3Sn, 18 Wedged Coils
• Cryostat: 29 m (H) x 28 m (D)
• Vacuum Vessel: 9 Sectors
• Port Plug: H&CD, Diagnostics, Remote Handling
• Blanket: 440 Modules
• Vacuum, Extraction: 8 Units
• Divertor: 54 Cassettes

Timeline:

• 1992~2001: CDA, EDA (R&D)
• 2001: FDR (Baseline 2001)
• 2007: ITER Baseline 2007
• On 9 November 2012, French Prime Minister signed the official decree that authorizes the ITER Organization to create the Installation nucléaire de base (INB No.174) ITER.

Page 8 - ITER Component Sharing

ITER Component Sharing

• Feeders: China
• Toroidal Field coils (18): China, EU, Japan, Korea, Russia, USA
• Poloidal field coils (6): China, EU, Russia
• Correction coils (18): China
• Central solenoid (6): Japan, USA
• Divertor: EU, Russia, Japan
• Blanket modules: China, EU, Korea, Russia, USA
• Vacuum vessel: EU, Korea, Russia, India
• Thermal shield: Korea
• Cryostat: India

Page 9 - Vacuum Vessel Procurement Sharing

Vacuum Vessel Procurement Sharing

Total: 234.28 kIUA (8% of total in-kind)

Breakdown by Party:

• EU:
  • Items: 7 Sectors of Main Vessel
  • Total Cost: 92.06 kIUA (39%)
• RF (Russia):
  • Items: 18 Upper Ports
  • Total Cost: 20.86 kIUA (9%)
• KO (Korea):
  • Items: 2 Sectors of Main Vessel, 17 Eq. & 9 Lower Ports
  • Total Cost: 84.06 kIUA (36%)
• IN (India):
  • Items: In-Wall Shields/Ribs
  • Total Cost: 37.30 kIUA (16%)

Page 10 - In-kind Contribution of Korea

In-kind Contribution of Korea

Total Value: 259.60 kIUA

1. TF Conductor (Completed): Total Value: 215.01 kIUA | KO Allocation: 20.2% | KO Contribution: 43.39 kIUA
2. Vacuum Vessel Main Body: Total Value: 118.51 kIUA | KO Allocation: 21.3% | KO Contribution: 25.20 kIUA
3. Vacuum Vessel Port: Total Value: 76.98 kIUA | KO Allocation: 72.9% | KO Contribution: 56.13 kIUA
4. Thermal Shield: Total Value: 26.88 kIUA | KO Allocation: 100% | KO Contribution: 26.88 kIUA
5. Blanket Shield Block: Total Value: 56.34 kIUA | KO Allocation: 49.8% | KO Contribution: 28.07 kIUA
6. Assembly Tooling: Total Value: 18.45 kIUA | KO Allocation: 100% | KO Contribution: 18.45 kIUA
7. Tritium SDS: Total Value: 12.51 kIUA | KO Allocation: 94.2% | KO Contribution: 11.79 kIUA
8. AC/DC Converters: Total Value: 122.61 kIUA | KO Allocation: 37.1% | KO Contribution: 45.58 kIUA
9. Diagnostics: Total Value: 205.66 kIUA | KO Allocation: 2.0% | KO Contribution: 4.11 kIUA

Test Blanket Module*:

• KO Contribution: HCCR TBS (TBM System)
• kIUA Value: N/A

• TBMA (TBM Arrangement) was signed in 2014.

Page 11 - Procurement Schedule of KODA

Procurement Schedule of KODA

• Procurement schedule according to the new ITER baseline schedule (2025 FP and 2035 DT)

Timeline overview (~2013 to 2028) covering milestones (PA, Contract Award, 1st Delivery, Last Delivery) for:

• TF Conductor
• Main Vessel
• Vacuum Vessel E/L Ports
• Blanket SB
• Assembly Tooling
• Thermal Shield
• AC/DC Converters
• IVC Bus bar
• Diagnostics
• Tritium SDS
• TBMA

Page 12 - Contents (Section 2)

Contents

1. Overview of KO ITER Project
2. Activities of KODA Procurement
3. Summary

Page 13 - TF Conductors (completed work)

TF Conductors (completed work)

• KO TF conductors (20.18 %) consist of 19 rDPs (760 m) and 8 sDPs (415 m).
  • TF Conductor Performance Qualification Sample test had been passed on 5 November 2008.
  • Production of strands and cablings was completed in 2013 and in May 2014, respectively.
  • Strand Diameter: 0.82mm, Cable: 900 Nb3Sn + 522 OFHC strands, CICC: 760m (19) + 415m (8)
  • All 27 TF conductors were delivered to JADA by the end of November 2014, on schedule.
  • This is the first procurement item successfully accomplished by KODA.
  • Key technology is an optimized design on Twist Pitch Combination & Void Fraction.
• SULTAN Test:
  • K10 samples from 10 Conductor ULs were tested at SULTAN after PA signature.
  • A lesson learned: sampling for quality control would be optimized (10 %, e.g.).
  • Graph shows Tcs (K) values across samples KO4L to KO8R meeting criteria.

Page 14 - Manufacturing Process of TF Conductors

Manufacturing Process of TF Conductors

• 900 Nb3Sn and 522 copper Strands are assembled into a multistage, rope-type Cable which is inserted into a conduit of butt-welded stainless steel Jacket Sections and compacted (Cable In Conduit Conductor).
• Optimized Twist Pitch Combination & Void Fraction ([45/85/125/250/450] -> [80/140/190/300/420] mm: 33 % -> 30 %)

Cabling diagram & cross section:

• Nb3Sn strand (diameter 0.82) -> x3 -> x3 -> x5 -> x5 (+ Cu cables)
• Cu strand (diameter 0.82) -> x3 x 4 Cu cables
• Sub cable wrap SS316L (0.05mmt) 50% coverage
• Cable wrap SS316L (0.08mmt) 50% overwrap
• Center Channel (diameter 7 / diameter 9), Outer conduit diameter 41.1

Page 15 - Manufacturing Process of TF Magnets

Manufacturing Process of TF Magnets (Slide by JADA)

Process Flow:

1. TF conductor (CN, JA, KO, EU, RF, US) -> Winding
2. Radial Plate (RP) Winding & Insertion -> Heat Treatment (HT 650°C, >100h) with elongation caused by HT
3. Transfer into RP grooves
4. Insulation & Taping Head -> Winding Pack (WP)
5. Coil case sub-assemblies -> Assembly (WP & Case)

Page 16 - Structure of ITER TF Magnets

Structure of ITER TF Magnets (Slide by JADA)

Dimensions & Specs:

• Dimensions: 9 m width x 16.5 m height
• Field: 11.8 T
• Current: 68 kA
• Weight: ~300 tons
• Subassemblies of coil case + Winding pack (110 tons)

Cross-sectional view of a TF winding pack (WP) (Inboard):

• Regular double pancake (DP) (5), Side DP (2)
• Turn insulation, Insulation around DP
• Cover plate (CP) laser welded between RP and CP
• RP groove to insert conductor
• TF conductor (Nb3Sn CICC)

Page 17 - Vacuum Vessel Sectors

Vacuum Vessel Sectors

• Functions:

  • Provide high vacuum for plasma operation
  • First safety barrier (PIC) for radioactive materials
  • Support all in-vessel and port components

• KO Packages:

  • Procurement Sharing of VV: 2 sectors of Main Vessel (#6, #1); 2 additional VV sectors from IO (#7, #8)
  • Major Dimension of MV: Outer Diameter: 13.8 m | Height: 6.6m | Weight: 410 ton (assembled sector)

• Technical Challenges:

  • The VV is very complex confinement structure with double walls, made of 60mm thickness 316L(N)-IG plate.
  • Application of unexperienced stringent French nuclear regulations such as ESPN, PED, RCC-MR Code, EN std, etc.
  • 100% Volumetric Examination for Pressure Bearing parts
  • 100% Visual Inspection on Backside Welding
  • Very tight manufacturing tolerances, even a huge welded stainless steel structure having uncountable weld seams and deformations

Major dimensions & weight table:

• Outer diameter: 19.4 m | Main vessel: 1611 ton
• Height: 11.4 m | Shielding: 1733 ton
• Double wall thickness: 0.34-0.75 m | Ports: 1781 ton
• Interior surface: 850 m² | Supports: 111 ton
• Interior volume: 1600 m³ | Total: 5236 ton

Page 18 - Manufacturing Process of Vacuum Vessel Main

Manufacturing Process of Vacuum Vessel Main

Step-by-step manufacturing illustrations:

1. Fabrication of triangular supports & Cutting/forming
2. Welding between supports
3. Welding of port stub
4. Welding of inner shell to inner shell
5. Preparation of outer shell
6. Welding of outer shell
7. Sector assembly and integration into full 360° torus

Page 19 - Manufacturing of Vacuum Vessel (Technology Development)

Manufacturing of Vacuum Vessel (Technology Development)

• Welding and NDE of 100% Volume by (nuclear) ESPN:

  • 316L(N)-IG GTAW (165 mm), EB welding (60 mm)
  • 100% Volumetric NDT: RT (basic) and PAUT (by using Omni Scan MX)
  • UT qualifications: very difficult due to complicate shape & access

• Tight tolerance: Metrology and GD&T analysis process:

  • 3D Measurement: Equipment: AT401 Laser tracker (1.5”/0.5” SMR & Retro Probe), Analyzing S/W: SpatialAnalyzer
  • GD&T Analysis: Best-fitting with instrument and points, USMN for multi-bundle measuring, Align to the datum
  • Application of GD&T: Applying GD&T analysis for fabrication optimization; Given step is applied for every measuring process

Page 20 - Manufacturing Progress of Vacuum Vessel Main

Manufacturing Progress of Vacuum Vessel Main

• Vacuum Vessel Main Status:
  • Manufacture of VV Sectors by HHI is ongoing in order to ensure First Plasma in December 2025, but with many technical challenges;
  • Manufacturing progress of the first Sector #6 is 85.6% (end of December 2018).
  • Sector 7 is 70.4%, Sector 8 is 50.5% and Sector 1 is 37.2% (end of December 2018).

Photographs:

• Poloidal Segment #2 (PS2): T-rib, Flexible Support Housing and In-Wall Shielding Support Rib Assembly
• Poloidal Segment #3 (PS3): Outer Shell Welding Assembly
• Poloidal Segment #4 (PS4): IWS Block Assembly

Page 21 - Vacuum Vessel Ports

Vacuum Vessel Ports

• Functions:

  • To support the in-port components (such as RF Antenna, test modules, etc.)
  • To provide access for in-vessel components, maintenance equipment, diagnostics and plasma heating equipment

• KO Packages:

  • 9 sets of Lower PSEs
  • 9 sets of Lower PEs / Lower Penetrations
  • 14 sets of Eq. Regular ports
  • 1 sets of H/DNB Port
  • 2 sets of HNB Ports
  • 3 sets of NB IWS
  • 9 sets of VV Gravity Supports
  • 3 sets of NB Duct Liner
  • Closure Plates & Sealing Flanges

Page 22 - Manufacturing Progress of VV Ports

Manufacturing Progress of VV Ports

• VV Ports Status:
  • Factory Acceptance Test (FAT) of the first Lower Port Stub Extension (LPSE 10) was completed and manufacturing of remaining LPSEs is in progress on schedule;
  • All Lower Port Extensions (LPE) and Neutral Beam Port Stub Extensions (NB PSE) are being manufactured.

Photographs:

• 3D inspection before Factory Acceptance Test of LPSE
• Factory Acceptance Test (Pressure Test) of LPSE 10
• Phased Array UT (NDE) inspection on Shield Plate weldment of NB PSE

Page 23 - Thermal Shields

Thermal Shields

• Functions:

  • Thermal shield (TS) minimizes radiation heat loads from warm components (vacuum vessel and cryostat) in order to protect superconducting magnet.
  • Emissivity < 0.05 (Ag coating 5 µm with surface Ra<0.24 µm)
  • 80K structure of 304LN, cooled by pressurized He gas (1.8 MPa)

• KO Packages of 100% Thermal Shield:

  • Upper Cryostat Thermal Shield (UCTS) - 110 ton
  • Lower Cryostat Thermal Shield (LCTS) - 95 ton
  • Equatorial Cryostat TS (ECTS) - 285 ton
  • Vacuum Vessel Thermal Shield (VVTS) - 384 ton
  • Support Thermal Shield (STS) - 28 ton
  • TS Manifold (TSM)
  • TS Instrumentation (TSI)
  • TS Main Components: 21 m diameter x 15 m height (+5 m base)

• Status of TS Manufacturing:

  • Preassembly of VV Thermal Shield (VVTS) Sector #6 (23 pieces) was completed;
  • FAT (Factory Acceptance Test) of LCTS cylinder was completed;
  • Silver coating of LCTS cylinder was completed;
  • Progress of Thermal Shield manufacturing is about 73% (end of December 2018).

Page 24 - Manufacturing of Thermal Shields (Technology Development)

Manufacturing of Thermal Shields (Technology Development)

• Tight Tolerance:

  • Manufacturing with assembly of 23 pieces to meet rigorous tolerance
  • Plate size of VVTS: 12,000mm (height), 20mm (thickness) -> tolerance: 2mm
  • (Images: VVTS Inboard Pre-assembly, VVTS 20-deg. Outboard Pre-assembly)

• Endoscope Inspection:

  • Requirement: 100% visual inspection inside surface of cooling pipe after welding on the panel to detect possible burn-through or depression, etc. (Pipe ID: 9.24mm, thickness: 2.24mm, total length: 35m bended)
  • Issue: Impossible to insert a conventional endoscope into 35m pipe
  • Solution: Development of novel endoscope (low friction ring spacer, compressed air pushing concept)

Page 25 - Thermal Shields: Silver Coating Technology

Thermal Shields: Silver Coating Technology

• Silver Coating against big-size stainless structure for low emissivity:
  • The thermal shield shall be electroplated by silver of 5 um to maintain its emissivity below 0.05.
  • The process and facilities for the ITER TS is challenging due to its huge size and complex shape.
  • Silver coating process lines consist of 11 baths, having the inner size of 9 m(L) x 3 m(W) x 6 m(H), which can accommodate the largest part of the ITER thermal shield.

Page 26 - Blanket Shield Blocks

Blanket Shield Blocks

• Functions:

  • Absorb radiation and particle heat fluxes from the plasma and the Neutral Beam
  • Contribute in neutronic shielding to the vacuum vessel and external vacuum components

• Material & Specs:

  • Stainless Steel 316L(N)-IG
  • Size: (about) 1.5 x 1.0 x 0.5 m
  • Weight: (about) 2.6 ton/each
  • Number: 440 modules (Total)
  • KO Allocation: 220 modules (CN: 220)
  • (Illustrations showing FW Panel, Shield Block, and KO Shield Block distribution around poloidal sections SB01–SB16)

Page 27 - Blanket Shield Blocks: Key Technology

Blanket Shield Blocks: Key Technology

• Hot Helium Leak Test:

  • Protocol: number of heating cycles; use of N2-gas; need of pressurization cycles;
  • Measurements: hydrogen outgassing difficulty to attain the sensitivity at high temperature;

• Low Friction Coating (MoS2) on the Female thread of FW central Bolt insert:

  • Technical Specification of Low-Friction/Anti-seize coating (friction coefficient: 0.05~0.1) is very challenging in the following requirements of 2,500 sliding cycles;
  • Roughness: all the surfaces to be coated shall be a recorded roughness measurement.
  • Surface finishing: the bolt and nut threads shall be a final surface roughness <= Ra 0.4 µm.
  • Coating uniformity: the coating thickness should be 2+/-0.5 µm.

• Tight Tolerances of Inlet/Outlet:

  • Requirements (3 +/- 0.05 mm) of the dimensional tolerances on Inlet/Outlet was checked by KODA R&D through development of a special tool set.
  • (Images: Hydraulic connector, FW panel assembly drawings)

Page 28 - ITER Assembly Process

ITER Assembly Process

Process Flow Diagrams:

1. Assembly Hall & Tokamak Complex setup
2. Lower Cryostat Activities Tools
3. Sector Sub-Assembly Tools (assembling Vacuum Vessel sector with Thermal Shields and TF coils)
4. Sector Assembly Tools (transport and placement in pit)
5. In & Ex-Vessel Activities Tools

Page 29 - Assembly Tooling (1/2)

Assembly Tooling (1/2)

• KO Packages of Assembly Tools (100% of major tools):

  • Sector Sub-assembly Tools, Sector Assembly Tools, Ex-Vessel Assembly Tools

• Sector Sub-assembly Tool:

  • Handling heavy components up to 1,200 t
  • 6 DoF (radial, toroidal, vertical translation & rotation) alignment: (+/- 1 mm precise control)
  • Dimensions and weight: 16.7 m (L) x 16.5 m (W) x 22.6 m(H) and 820 t
  • (Photographs showing fabrication and trial assembly of large steel structures)

Page 30 - Assembly Tooling (2/2)

Assembly Tooling (2/2)

• SSAT-1 FAT at the KO Factory and SAT at the ITER Site (+/- 1 mm precise control):
  • The first Sector Sub-Assembly Tool (SSAT) #1 was delivered to IO in June 2017.
  • Assembly/Installation activities of the SSAT-1 in the ITER Assembly Building have reached 90 % progress and now it is almost ready to the Site Acceptance Test by IO.
  • The second SSAT #2 is under transportation to IO since July 2018.
  • (Photographs showing Site Installation of SSAT-1 in the ITER Assembly Building at Cadarache)

Page 31 - AC/DC Converters (1/3)

AC/DC Converters (1/3)

• Functions:

  • Provide required current for TF, CS, PF, CC coils
  • Cooperate protection of power supplies and coils
  • Integrate the coil power supply I&C by MCS

• Manufacturing status:

  • First CCU/L, CCS, VS1, CS converters are completed.
  • First TF converters are under manufacturing.
  • Master Controllers (CC, TF, PFCS) are completed.

• Factory Acceptance Test:

  • Assembly of AC/DC converter for FAT with same configuration as ITER installation
  • FAT of first CCU/L, CCS, VS1 converters is completed.
  • FAT of all CCU/L, CCS, VS1, CS transformers is completed.
  • First CCS, VS1 transformers were placed at ITER site in January 2018.

• Key Technology:

  • Converter topology optimization design (site adaptation)
  • Fabrication feasibility of high-power thyristor rectifier unit
  • Short circuit test (facility)
  • Seismic structure analysis

• Diagrams: Configuration of AC/DC Converter; Configuration of ITER Coil Power Supply System (400 kV Substation, Coil Power Supplies, Tokamak, NB H&CD, RPC, RF HCD)

Page 32 - AC/DC Converters (2/3)

AC/DC Converters (2/3)

• 17 units of transformers (6 CCU/L, 3 CCS, 2 VS1, 6 CS): delivered to ITER site
• CS transformer weight (89 tons) is close to maximum capacity of FOS crane (90 tons).
  • Considering +/- 5% crane tolerance, heavy lift ship having own 2 cranes (450 tons) is used.
• (Photographs of heavy transport, barge shipment, and crane handling of transformers)

Page 33 - AC/DC Converters (3/3)

AC/DC Converters (3/3)

• Installation Progress of Transformers:

  • Contract with local company (FATSUR): April 2018
  • Start of site work: May 2018 (Teamwork of IO/CMA - KODA/Supplier - Local Company)
  • Installation work has been completed for VS1 (2), CCU/L (4), CCS (3), CS (3) transformers in October 2018.
  • (Images: Bldg. 33, VS1 Transformer; Bldg. 33, CCS Transformer; Bldg. 32, CS Transformer)

• Preparation for Installation of Converters: Restrictions to Installation Plan:

  • Floor: strength for heavy components and roughness for air pad
  • Beam structure: Crane/Hoist applicability
  • Non-routine lifting, CoG unbalance

Page 34 - Tritium Storage & Delivery System (1/3)

Tritium Storage & Delivery System (1/3)

• Key Technologies to be developed by KO-DA:

  • Process design, fabrication and delivery (2 kg T inventory)
  • Tritium storage bed design & fabrication (70 g T)
  • Tritium inventory accountability

• On-going R&D Works (PD R&D Phase):

  • SDS getter (DU) bed 1:1 mock-up test (with 2 kg DU)
  • SDS unit process feasibility verification test
  • Tritium inventory calorimetry, He-3 recovery
  • SDS modeling, Fuel cycle modeling

• Schedule:

  • CD (May 2014), PD (Oct. 2020), PA (Jun. 2021), FD (2023), Delivery (2027~28)

• Images: ITER Tritium Plant showing SDS in B1 Level with Four Rooms; DU Bed (1:1 Mock-up); DU SDS Process Verification Experiment facility

Page 35 - Tritium Storage & Delivery System (2/3)

Tritium Storage & Delivery System (2/3)

• Uranium Hydride Reaction via Visual Cell Reactor:
  • Micro-sizing after 3 cycles of hydride (room temp.) /dehydride (450°C)
  • -> Need 0.5 um sintered metal filter for safety
  • -> Requirements: 4,000 hydride/dehydride cycles

Visual cell progression photos:

• Initial, 6 min., 10 min., 21 min., 30 min., 45 min., 85 min. (Gradual surface change and volume expansion of DU by 1st hydriding)
• SEM images: After one cycle, After three cycles, After ten cycles (DU powder after number of hydriding/dehydriding cycles).

Page 36 - Tritium Storage & Delivery System (3/3)

Tritium Storage & Delivery System (3/3)

• Metal (DU) Hydride Bed: 4,000 hydride/dehydride thermal cycles:

  • Hydriding & dehydriding reactions with thermal cycles: after cycles, DU is pulverized and spread into the space of Cu foam so that the Cu foam is squeezed by rapid volume expansion of DU.
  • Cu foam installation to enhance heat transfer inside a DU bed

• Figures:

  • Fabrication model of DU hydride bed
  • Graph: Dehydriding reaction of the DU bed (Pressure vs Time vs Temperature)
  • Cross section showing Cu foam deformation with hydride/dehydride reactions

Page 37 - Diagnostics (1/3)

Diagnostics (1/3)

• Functions: Diagnostic systems shall measure the plasma and the plasma facing surfaces for: (1) basic machine control, (2) machine protection, (3) advanced plasma control, (4) physics study.

• KO procures 5 systems among > 100 ITER diagnostic systems.

• KO Procurement package:

  • Three VUV Spectrometers for impurity measurement:
    • Core (C/N/O), edge (Be), divertor (W)
  • Neutron Activation System (NAS):
    • first wall fluence and total neutron flux
  • Upper Port #18 Port Integration (UP18 PI):
    • diagnostic integration and infrastructure in UP#18

• Diagrams: VUV Spectrometer (Edge Imaging, Core Survey/divertor), NAS, UP18 PI layout.

Page 38 - Diagnostics (2/3)

Diagnostics (2/3)

• KO-DA diagnostics are at the preliminary and final design phase for now.

  • Timeline: Design (2018-2020), Manufacturing and Delivery (2019-2026), Installation and Commissioning (2020-2028)

• VUV Spectrometer:

  • Mirror protection: (1) shutter and feedthrough (2) deposition mitigation system
  • Neutron and gamma shielding for CCD camera
  • Fabrication of VUV sample mirror: 0.5-1 nm roughness (Au coated SS mirror)

• Photographs: Shutter test at KSTAR, VUV sample mirror, and 3D simulation of normalized neutron flux distribution with 20 cm thick borated PE base shielding and 10cm additional shielding plates.

Page 39 - Diagnostics (3/3)

Diagnostics (3/3)

• Neutron activation system (100~200 m):

  • Capsule: pneumatic transfer (~10 m/s) of activation sample, made of CFC
  • Activation sample: In, Si, Cu, etc.
  • Capsule position monitoring system
  • High thermal load on the irradiation stations
  • Many interfaces with other PBS systems

• Upper port #18 port integration:

  • Integration of 3 diagnostics: VUV (KO), NAS (KO), and UVNC (RF)
  • Neutron shielding: shutdown dose rate
  • Development of pipe feedthrough

• Illustrations: Capsule design (CFC Upper and Bottom parts), Capsule transfer line design through building levels (L3, L2, L1, B1), Neutron flux calculation plot, Upper port #18 integration assembly.

Page 40 - HCCR (Helium Cooled Ceramic Reflector) TBM (1/2)

HCCR (Helium Cooled Ceramic Reflector) TBM (1/2)

• Functions:

  • To demonstrate tritium breeding capability
  • To extract high-grade heat for electricity generation

• System Configuration:

  • Vacuum Vessel: TBM-set (TBM body / TBM shield) inside Common Frame/Duct
  • Port Inter-space & Port Cell (Tokamak L1): TBM Systems in Port Cell (Pipe Forest / bio-shield / Ancillary Equipment Unit [AEU])
  • TCWS VA (Room 14-L4-20): Part of Helium Cooling System (HCS) inc. Coolant Purification System (CPS)
  • Tritium Building (Room 14-L2-24): Tritium Extraction System (TES), Neutron Activation System (NAS), Tritium Accountancy System (TAS)

• 3D CAD Renderings: TBM-set with frame, Pipe Forest, AEU, HCS, TES.

Page 41 - Test Blanket Module (2/2)

Test Blanket Module (2/2)

• KO Helium Cooled Ceramic Reflector (HCCR) TBM (DEMO-relevant breeding breeder concept)

Parameters & Values:

• FW heat flux: 0.3 MW/m²
• Neutron wall load: 0.78 MW/m²
• Thermal Power: 0.98 MW
• Structural material: KO-RAFM (ARAA) (< 550°C), 0.01% Zr (Improved creep and impact resistances)
• Breeder: Li2TiO3 (< 920°C), ~80 kg, 70% enrichment Li-6
• Multiplier: Be (< 650°C), ~100 kg
• Reflector: Graphite (<1200°C) (Reduce the Be Multiplier up to 50%)
• Size: 1670(P) x 462(T) x 605(R) (mm)
• Coolant: 8 MPa He, 1.14 kg/s (Nominal), 300°C inlet / 500°C outlet
• Purge gas: He with 0.1 % H2
• TBM-shield: 316L(N)-IG Block/Cooling Channels, ITER FW/BLK-PHTS (40°C, 4 MPa)

Images: Sub-module structure (Reflector, Breeder, Multiplier, FW, SW), mock-up fabrication steps, ARAA (Advanced Reduced Activation Alloy) product bars.

Page 42 - Contents (Section 3)

Contents

1. Overview of KO ITER Project
2. Activities of KODA Procurements
3. Summary

Page 43 - Overall Physical Progress of KODA Procurement Activities

Overall Physical Progress of KODA Procurement Activities

Overall Physical Progress of KODA Procurement Activities (including design) is recorded as about 64.2% in October 2018 (Average calculated as Activity Progress as per Item x Weight of its kIUA).

Progress by Item (as of October 2018):

• TF Conductors: 100.0%
• Vacuum Vessel Sector: 85.5%
• Vacuum Vessel Ports: 41.3%
• Thermal Shield: 65.5%
• Blanket Shield Blocks: 24.5%
• Assembly Tools: 89.0%
• Tritium SDS: 13.3%
• AC/DC Converters: 76.1%
• Diagnostics: 30.7%

Page 44 - ITER Roles for K-DEMO Technology

ITER Roles for K-DEMO Technology

• Fusion Plant EPC Technology (in the Construction Phase): => Key Construction Technology for K-DEMO:

  • Engineering design and manufacturing (Codes & Standards) of components/systems (VV, SCM) and buildings for Tokamak reactor construction
  • Remote handling, maintenance, repair under the radioactive environment
  • Systems of CODAC, Heating and Current Drives, and Diagnostics => License Technology for Safety of K-DEMO:
  • Licensing and Environmental Safety, etc. -> Safety Analysis & Preliminary Safety Report (RPrS) => Project Lifecycle Management Technology for K-DEMO Project:
  • Managements of Quality, Performance, Risk, Interface, Baselines, Engineering Dossiers, etc.

• Physics and Operation Technology (in the Operation Phase): => Burning Plasma Physics Understanding:

  • Burning plasma operation, integrated operation scenarios, integrated plasma control
  • Alpha particle: Plasma stability, MHD, ELM & disruption mitigation, transport & confinement
  • Divertor and plasma-wall Interactions

• Fusion Reactor Engineering => Test Blanket Modules:

  • Breeding blankets (tritium extraction), etc.
  • Tritium fuel cycle (exhaust processing, detritiation, isotope separation, etc.)
  • Blanket/Divertor (W) materials under the heavy heat and nuclear loads

Page 45 - Summary

Summary

• The ITER project is a first-of-a-kind fusion reactor enterprise that has the technical challenges inherent. So, it is important for world-wide fusion communities to make their common efforts towards the success of ITER.
• International Enterprise is a challenge on how to control and manage the quality of in-kind components/systems.
• KO-DA is working collaboratively with the IO and other DAs to meet the FP in 2025.
• KO-DA procurement activities are actively progressing for design and manufacturing.
• ITER Korea is very keen to accumulate the core fusion technology of ITER tokamak systems, including non-KO procurement items.
• Systematic approach with coordinated strategy for fusion programs in Korea is very important to integrate not only all of the key technologies but also human resources and infra-structures to develop a DEMO fusion reactor.
• The success of ITER would give a big momentum to the KO fusion community to undertake a fast track to build the commercial fusion power plant in the future.

Page 46 - Korean Fusion Energy Development Roadmap

Korean Fusion Energy Development Roadmap

Roadmap Diagram:

• KSTAR -> Fusion Plasma Research -> ITER & DEMO Physics Support Activities -> ITER
• Blanket & Divertor Technology (Breeding Blanket, Structure Materials) -> Fusion Engineering Research -> TBM (Test Blanket Modules) -> ITER
• Structure Materials -> High Flux Neutron Irradiation Test -> Fusion Materials
• ITER + Fusion Materials + System Design -> Integrated System Design & Engineering -> DEMO Reactor -> Fusion Plant

Page 47 - Closing

National Fusion Research Institute

Thank you for your attention.

[Photo of flags of ITER member nations at the ITER site in Cadarache, France]