preliminary conceptual design study of k-demo

Preliminary Conceptual Design Study of K-DEMO

Japan-US WorkshopFebruary 26th, 2013

Advanced Project DivisionNational Fusion Research Institute

[email protected]

Advanced Project Division

Introduction


Mid-Entry Strategy in 1995

PLT

ALCATOR C

PDX DIII

TFTR

DIII-D

JET/TFTR

JET

TFTRJT-60U

ALCATOR A

DEMO

1970 1975 1980 1985 1990 1995 2000 2005 2010

1KW

1MW

1GW

1W

SNUT-79

2015 2020 2040

JET

T-3(1968)

1965

ATCKAIST-TKT-1

KSTAR

ITERConventional Device (Cu)

Superconducting De-vice

SC Device

Fusi

on P

ower

Year3


KSTAR Superconducting Tokamak


KSTAR Device for 2012 Campaign

5

NBI-1 1st100 keV, 1.5 MW, 10 s

(KAERI, JAEA)

ECH84 GHz / 110 GHz

0.3 MW, 2 s(POSTECH, GA)

ECH (170 GHz)0.7 MW, cw(JAEA, PPPL)

ICRF 30-60 MHz,1 MW, 1 s

(KAERI)

LHCD5 GHz, 0.5 MW, 1 s

NBI-1 2nd100 keV, 2 MW, 10 s

2* ECE-I + MIR (POSTECH, UCD)

BES (8X8) (RMKI)

RMP PS4 kA/t (n=1, 2)

Thomson, 5 J, 100 Hz (JAEA, NIFS)

Div. IRTV

Reflectometer

Image Bolometer (NIFS)

FIR

MD, ProbesDa, VS, Filterscope (ORNL)

XICS, CES (NIFS), ECE (KAERI, NIFS)BES (RMKI), CI/2D MSE (ANU),

Interferometer, Bolometer (NIFS)SXR (KAIST), XPH (KAIST)

Fast ion loss, Neutron (Hanyang U, ITER KO)

VUV (ITER KO)


KSTAR In-vessel Control Coil System (3-D) Modular 3D field coils (3 poloidal x 4 toroidal)

- all internal and segmented with saddle loop configurations- 8 conductors in each coil- Control capability : vertical control, radial control, error correction,

RMP, RWM Wide spectra of Resonance Magnetic Perturbations (RMP) are

possible- n=1 RMP (phase angles : +90, -90, 180, 0) and n=2 RMP (even or

odd parity)

Schematics of IVCC and its conductor

topmidbot

+ + - -

- - + +- + + -

n=1, +90 phase

BP

topmidbot

+ - + -

- + - +

n=2, odd parity

topmidbot

+ - + -

+ - + -- + - +

n=2, even parity+

topmidbot

+ + - -

+ + - -+ + - -

n=1, 0 phase


βN-limit and ELM Suppression

Hα/RMP

2.7s 3.4s 4.3s

# 6123

ELM suppressed by n=1 RMP

(Ip = 600 kA, BT=1.6~2.3T)

KSTAR reached βN 〉 2.5 and βN/li 〉 4.0

“no-wall limit” in H-mode Op-eration

2012 New Data


Fusion Energy Development Promotion Law (FEDPL)

8

To establish a long-term and sustainable legal framework for fusion energy development phases.

To promote industries and institutes which participating the fusion energy development by supports and benefit.

The first country in the world prepared a legal foundation in fusion energy development.

• 1995. 12 : National Fusion R&D Master Plan• 2005. 12 : National Fusion Energy Development

Plan

• 2007. 3 : Fusion Energy Development Promotion Law

• 2007. 4 : Ratification of ITER Implementation Agreement

• 2007. 8 : Framework Plan of Fusion Energy Development

(The first 5-Year Plan)• 2012. 1 : The 2nd 5-year plan has begun

History of the FEDPL


Vision and Goal of Fusion Energy Development Policy

Acquisition of operating tech-nology for the KSTAR

Participation in the interna-tional joint construction of ITER Establishment of a system for

the development of fusion re-actor engineering technology

Establishment of a founda-tion for fusion energy de-

velopment

Secure sustainable new energy source by technolog-ical development and the commercialization of fu-

sion energyVision

Phase

Policy Goal

Basic Di-rections

Basic Pro-motion Plan

Primary Strategy for Plan-2

Basic Promotion Plan 1 (’07~‘11)

Attainment of KSTAR high-performance plasma and develop-ment of DEMO basic technologyBasic research in fusion and cultivation of man powerInternational cooperation and improvement of status in ITER operationsCommercialization of fusion/plasma technology and promotion of social acceptance

Phase 1 (’07~’11)

High-performance plasma opera-tion in KSTAR for preparations for

the ITER Completion of ITER and acqui-

sition of core technology Development of core technology for

the design of DEMO

Development of core technology for DEMO

Basic Promo-tion Plan 2 (‘12~‘16)

Phase 2 (’12~’21)

DEMO design, construction, and demonstration of electricity

production Undertaking of a key role in ITER

operations Completion of reactor core and sys-tem design of the fusion power reac-

tor Commercialization of fusion technol-

ogy

Construction of DEMO by ac-quiring construction capabil-

ity of fusion power plants

Phase 3 (’22~’36)

Basic Promo-tion Plan 3 (‘17~‘21)

Basic pro-motion plan 4 (‘22~‘26)



Policy Goal for Plan-2 R&D for DEMO Technology based on KSTAR and ITER


Korean Fusion Energy Development Roadmap

10

“Key Milestones”Pre-Concep-tual Design

Study

DEMO R&D

Launch & CDA

DEMO EDA Start

DEMO Final Design & Con-

str. Start

DEMO Phase-1 Construction

Finish


K-DEMO Tokamak Design


General Requirement (Two Phase Op-eration)

K-DEMO has two operation phases, Phase I and Phase II. Though the operation phase I K-DEMO does not need to demonstrate the competitiveness in COE(Cost of Electricity), the operation phase II K-DEMO need to demonstrate the competitiveness in COE.

All power core and plant subsystems in K-DEMO plant must be representative of those in the commercial plant. Extrapolation of technologies from K-DEMO to a commercial reactor should be straight forward. Practically all technologies to be used in commercial reactors should be demonstrated in the K-DEMO. Also, extrapolation of performance parameters be-tween K-DEMO and commercial reactors should be minimized.

K-DEMO shall be operated and maintained with remote handling equipment. This is an abso-lute prerequisite as the neutron level during operation and radioactive activation during maintenance periods will be excessive for human intervention inside the power core building and hot cell bio-shields at all times

The operation phase II K-DEMO plant need to achieve an overall all plant availability larger than 70%.

The operation phase I K-DEMO is not considered as the final DEMO. It is a kind of test facility for a commercial reactor. But the operation phase II K-DEMO will require a major up-grade by replacing the blanket & divertor system and others if required.

Construction cost for K-DEMO should be minimized and the size of the K-DEMO Tokamak is expected to be smaller or similar size of ITER Tokamak.

The operation phase I K-DEMO• At initial stage, many of ports will be used for diagnostics for the operation and burning plasma physics study, but

many of them will be transformed to the CTF (Component Test Facility).• At least more than one port will be designated for the CTF including blanket test facility.• It should demonstrate the net electricity generation (Qeng > 1) and the self-sufficient Tritium cycle (TBR > 1.05).

The operation phase II K-DEMO• Though there will be a major upgrade of In-Vessel-Components, at least one port will be designated for CTF for future

studies.• It is expected to demonstrate the net electricity generation larger than 450 MWe and the self-sufficient Tritium cycle .


Optimization Concept of K-DEMO Demonstrate a reasonable net-electricity (> 300 MW)

generation with a minimum cost

Provide a maximum flexibility

4 5 6 7 8 9 10 11 12012345678

BT(T)

βN

K-DEMO (Stage I)

CREST ARIES-AT

PPCS-D

ITER

ARIES-RS

SSTR

K-DEMO (Stage II)


K-DEMO Design ParametersBasic Parameter Option I Option II Option III

Major Radius 6.0 m 6.65 m 7.15 mMinor Radius 1.8 m 2.0 m 2.2 m

Elongation (k95) 1.8Magnetic Field (Bo)/Peak Field 7.5 Tesla / ~ 16 Tesla

Divertor Type Double Null (or Single Null)Bootstrap Current Fraction ~ 0.6

Normalized beta ~ 4.0Safety Factor (q95) 3.5~5.0

Plasma Current > 10 MA > 12 MA > 13 MATotal Fusion Power (Neutron) 1700 MW 2130 MW 2721 MW

Q-value 24 27 30Total H&CD Power 70 MW 80 MW 90 MW

Thermodynamic Efficiency 0.35Gross Electric Power 767 MW 958 MW 1220 MWRecirculating Fraction 0.7 0.6 0.55

Recirculating Electric Power 537 MW 575 MW 671 MWNet Electric Power 230 MW 383 MW 549 MW


DEMO TF CICC Parameter(Helical Spiral) Cable Pattern: (3SC)x4x6x6x(5+Spiral)[2160 SC strand] Void Fraction : 28.85% Strand :

• High Jc (> 2600A/mm2) Nb3Sn Strand• Cu/Non-Cu = 1.0

Helical Spiral : ID = 8 mm OD = 12 mm Insulation : 1.6 mm (with Voltage Tap)

• 0.1 mm Kapton 400% • 0.3 mm S-glass 400%

Jacket Thickness : 5.0 mm Twist Pitch

• 1st Stage 45 ± 5 mm• 2nd Stage 85 ± 10 mm• 3rd Stage 125 ± 15 mm• 4th Stage 245 ± 20 mm• 5th Stage 435 ± 20 mm

Wrapping Tape Thickness • Sub-cable : 0.08 m 40%• Sub-cable wrap width : 15 mm• Cable : 0.08 mm 140% • Final wrap width : 40 mm

SC Strand Weight : ~600 tonDEMO TF CICC Cross-section

44.0

74.0

1.6 5.0R 3

40.830.8

60.8

70.8Insulation

Jacket


DEMO Small TF CICC Parameter Cable Pattern: (3SC)x4x5x(6+Central Spiral)[360 SC

strand] Void Fraction : 31.03% Strand :


Central Spiral : ID = 7 mm OD = 10 mm Insulation : 1.6 mm (with Voltage Tap)



• 1st Stage 45 ± 5 mm• 2nd Stage 85 ± 10 mm• 3rd Stage 125 ± 15 mm• 4th Stage 335 ± 20 mm

Wrapping Tape Thickness • Sub-cable : 0.08 m 40%• Sub-cable wrap width : 15 mm• Cable : 0.08 mm 200% • Final wrap width : 40 mm DEMO TF CICC Cross-section

34.0

1.6 5.0

34.0

R 3

30.820.8

20.8

30.8Insulation

Jacket


Inboard Cross-Section of TF Coil (Op-tion I)

R = 6.0 m, a = 1.8 m Small CICC Coil : 16 x 8 turns Large CICC Coil : 12 x 5 turns (Total : 188

turns) Magnetic Field at Plasma Center : ~7.72 Tesla (Bpeak ~ 16 Tesla, T-margin

> 1 K) Nominal Current : 77.0 kA Conductor Length :

• LQP = ~777 m (Quadruple Pancake) Total : ~445 tons• SDP = ~634 m (Double Pancake) Total : ~163 tons

2050 mm

2890 mm2388 mm

2970 mm

ClearanceFilled with Glass Fiber (5 mm)

Ground Wrap(5 mm)

2660 mm


Outboard Cross-Section of TF Coil (Op-tion I)

198 mm

870mm

10910 mm

11780 mm

550

mm

ClearanceFilled with Glass Fiber(5 mm)Ground Wrap(5 mm)

11210 mm10990 mm112310 mm 11582 mm

278

mmSpace (Filled with

316) for Turn Tran-sition and Feed Through (90 mm)

106

mm


Inboard Cross-Section of TF Coil (Op-tion II)

R = 6.5 m, a = 2.0 m Small CICC Coil : 18 x 8 turns Large CICC Coil : 12 x 5 turns (Total : 204


> 1 K) Nominal Current : 76.9kA Conductor Length :

• LQP = ~825 m (Quadruple Pancake) (Total : ~480 ton)• SDP = ~680 m (Double Pancake) (Total : ~200 ton)

2150 mm3135 mm

2633 mm3220 mm

ClearanceFilled with Glass Fiber (5 mm)Ground Wrap

(5 mm)

2905 mm


Outboard Cross-Section of TF Coil (Op-tion II)

203 mm

880 mm

11810 mm

12690 mm

550

mm


11895 mm 12115

mm 12215 mm

12487 mm

Space (Filled with 316) for Turn Transi-tion and Feed Through (90 mm) 244

mm

106

mm


DEMO TF CICC Parameter(Option II-A) Cable Pattern: (3SC)x4x5x6x(5 + Helical Spiral) [1800 SC

strand] Void Fraction : 28.1% Strand :


Helical Spiral : ID = 8 mm OD = 12 mm Insulation : 1.6 mm (including Voltage Tap)



• 1st Stage 45 ± 5 mm• 2nd Stage 85 ± 10 mm• 3rd Stage 125 ± 15 mm• 4th Stage 245 ± 20 mm• 5th Stage 435 ± 20 mm

Wrapping Tape Thickness • Sub-cable : 0.08 m 40%• Sub-cable wrap width : 15 mm• Cable : 0.08 mm 140% • Final wrap width : 40 mm

DEMO TF CICC Cross-section

40.0

72.0

1.6

36.826.8

58.8

68.8

R 35.0

Insulation

Jacket


Inboard Cross-Section of TF Coil (Op-tion II-A)

Selected for Detailed Study R = 6.8 m, a = 2.1 m Small CICC Coil : 20 x 9 turns Large CICC Coil : 12 x 5 turns (Total : 240



• LQP = ~872 m (Quadruple Pancake) (Total : ~418 ton)• SDP = ~810 m (Double Pancake) (Total : ~258 ton)

2150 mm3135 mm

2619 mm3220 mm

2925 mm


Ground Wrap(5 mm)


Outboard Cross-Section of TF Coil (Op-tion II-A)

204 mm

925 mm

12210 mm

13165 mm

550

mm


12295 mm 12525

mm 12655 mm 12961 mm

Space (Filled with 316) for Turn Transi-tion and Feed Through (120 mm) 210

mm

118

mm


Inboard Cross-Section of TF Coil (Op-tion III)

R = 7.15 m, a = 2.2 m Small CICC Coil : 18 x 8 turns, Large CICC Coil : 12 x 6 turns (Total : 216



• LQP = ~ 1102 m (Quadruple Pancake) (~643 ton)• SDP = ~ 763 m (Double Pancake) (~218 ton)

2385 mm3395 mm

2849 mm

3480 mm


Ground Wrap(5 mm)

3121 mm


Outboard Cross-Section of TF Coil (Op-tion III)

204 mm

955 mm

13025 mm

13980 mm

550

mm


13110 mm

Space (Filled with 316) for Turn Transi-tion and Feed Through (120 mm)

13374 mm 13504

mm13776 mm

244

mm

106

mm


Joint Scheme of Inner MagnetFrom PS (or Inner Magnet Lead)

To Neighboring Inner Magnet Lead

Inter Coil Joint Inter Coil Joint

Layer Transition

Layer Transition

Layer Transition

HeliumFeed Through


Joint Scheme of Outer MagnetFrom Outer (or Last Inner) Magnet Lead

To Neighboring Outer Magnet Lead


3D Modeling of TF Magnet


3D Modeling of TF Assembly


TF Coil Structure


DEMO CS CICC Parameter (Corner Channel)

Cable Pattern: (3SC)x3x4x4x6 [864 SC strand] Void Fraction : 37.19% Strand :

• ITER Type (Jc ~ 1050A/mm2) Nb3Sn Strand• Cu/Non-Cu = 1.2

NO COOLING SPIRAL Corner Channel Jacket Thickness : 5 mm Insulation : 2.0 mm (with Voltage Tap)


Twist Pitch• 1st Stage 45 ± 5 mm• 2nd Stage 85 ± 10 mm• 3rd Stage 145 ± 10 mm• 4th Stage 250 ± 15 mm• 5th Stage 420 ± 20 mm

Wrapping Tape Thickness • Sub-cable : 0.08 mm 40%• Sub-cable wrap width : 15 mm• Cable : 0.5 mm 60% • Final wrap width : 7 mm

DEMO CS CICC Cross-section

54

34

20

40

R 32 5

50

30

Insulation

Jacket


Cross-Section of CS Coils (Option I) Number of Turns : 14 (Total SC strand weight : ~120 tons)

Number of Layers : CS1 & CS2 : 30 layers, CS3 : 24 layers Magnetic Field at Center : ~12.52 Tesla (Bpeak < 12.774 Tesla) Conductor Unit Length : 895 m (CS1 & CS2 : UL x 5, CS3 : UL x 4) Gap Between Coils : 50 mm

CS1 & CS2 Coil CS3 Coils

1620

mm

1896 mm1420 mm1896 mm1420 mm

1296

mm


Magnetic Field of CS Coils (Option I) Magnetic Field

• Field at Center : ~12.835 Tesla • Peak Field : ~ 13.086 Tesla• Maximum Flux Swing : ~81 V·sec

Nominal Current : 44 kA (Current can be increased) Temperature Margin ~ 1.4 K


Cross-Section of CS Coils (Option II) Number of Turns : 14 (Total SC strand weight : ~145 tons)

Number of Layers : CS1, CS2 & CS2 : 30 layers Magnetic Field at Center : ~13.12 Tesla (Bpeak < 13.37 Tesla) Conductor Unit Length : 950 m (CS1, CS2 & CS3 : UL x 5) Gap Between Coils : 50 mm

CS1 & CS2 & CS3 Coil CS3 Coils

1620

mm

1976 mm1500 mm


Magnetic Field of CS Coils (Option II) Magnetic Field




Cross-Section of CS Coils (Option III) Number of Turns : 14 (Total SC strand weight : ~165 tons)

Number of Layers : CS1, CS2 & CS2 : 30 layers Magnetic Field at Center : ~13.1 Tesla (Bpeak < 13.35 Tesla) Conductor Unit Length : 1070 m (CS1, CS2 & CS3 : UL x 5) Gap Between Coils : 50 mm

CS1 & CS2 & CS3 Coil CS3 Coils16

20 m

m

2206 mm1730 mm


Magnetic Field of CS Coils (Option III) Magnetic Field




Test Samples of Conductors

DEMO CS CICC(corner channel) & Large TF CICC (helical spiral)

Thanks to Antonio della Corte & his colleagues (ENEA/ICAS) !!


Concept of Vertical Maintenance (Pilot Plant)

Vertical maintenance of all in-vessel components for Pilot Plant (PPPL) Case

DCLL PbLi/He Base Blanket (350/450° C)

VV (~150° C)

Gravity support / coolant supply

plenum

Internal VV maintenance

space expanded

Coolant supply from below

Horizontal assisted maintenance

Horizontal assisted maintenance

Enlarged TF

Semi-permanent Inboard Shield

structure (~350° C)


3D Modeling of Blanket System


Assumption for the Thickness of BlanketInboard-Side Blanket [Thickness = 1000 mm]

Outboard-Side Blanket [Thickness = 1225 mm]

Blan-ket

200 167

Shield

150 8550

Be

38 240

Manifold & Structures

FW

Be

70

W Li4SiO4 Coolingchannel

Be B4C

200 280

Manifold & StructuresShield

Blan-ket

200150 8550

Be

40

FW

Be

100 100 20

Struc-tural

Material


Radial Build of K-DEMO [unit : mm] (Option I)

PlasmaCS TF Blan-ket Blanket VV TFVV

142018962050

300031703300 410

04200

SOL SOLTS

6000 780

07900

101001048

01091011780

TS

9100

Space for Vertical

Maintenance


Radial Build of K-DEMO [unit : mm] (Option II)


150019762150

322034203550 455

04650

SOL SOLTS

6650 865

08750

111751155

51198512895

TS

9975

Space for Vertical

Maintenance


Radial Build of K-DEMO [unit : mm] (Option II-A)


150019762150

322034203550 460

04700

SOL SOLTS

6800 890

09000

114001178

01221013135

TS

10200

Space for Vertical

Maintenance


Radial Build of K-DEMO [unit : mm] (Option III)


173022062385

348036803850

48504950

SOL SOLTS

765093509450

121751257

51302513980

TS

10675

Space for Vertical

Maintenance


K-DEMO Conceptual Study & CDA Schedule

Target Date for K-DEMO Construction : End of 2037

2012.1~2012.12

2013.1~2013.12

2014.1~2014.12

2015.1~2017.12 2018.1~2021.12

Pre-study Pre-study Report

Design Parameter OptionsPhysics & Backup Study (Phase I)

Pre-Conceptual Design Study ReportImprovement of Report

CDA Phase ICDA Phase II + CDR

Physics & Backup Study (Phase II)

★

★


SUCCEX Facility


Requirement Split pair solenoid magnet system Inner bore size : ~1 m Maximum magnetic field : ~16.39 Tesla Magnetic field at center : ~ 15.33 Tesla Maximum Helium flow channel length : < 100 m

• One magnet of the split pair consists of three coil (IC, MC, OC) and the maximum of Helium channel length should be maintained below 100 m

• Every double pancake of each coil will have Helium inlet and outlet• Each coil have a number of inter magnet joints because of the maxi-

mum fabrication capability in the length of CICC Test Mode

• Semi-circle type conductor sample test mode U-shape sample with the bottom radius of 0.5 m DEMO TF conductor will have a rectangular cross-section to reduce the strain effect & will

have capability of a minimum bending radius of 0.5 m No joint : no question regarding voltage arising from the joint There are enough distance for the voltage relaxation from the sample terminal to voltage

taps• Sultan like sample test mode

For the case of CS conductor, the size of the is expected to be a range of 50 mm. And it is not easy to make the U-shape sample because of the minimum bending radius

Also the facility could support the joint technology development


Coil Parameters Gap Between Upper and Lower Coil : 140 mm Operating Current : 18 kA Peak Field : 16.39 Tesla Center Field : 15.33 Tesla Number of Strand per CICC

• IC : 360 strands• MC : 244 strands• OC : 72 strands

Conductor Size (Including 1.0 mm insulation) • IC : 18 x 37 mm • MC : 16 x 30 mm• OC : 15 x 29 mm

Jacket Thickness• IC : 3 mm• MC : 3 mm• OC : 2.5 mm

Insulation : 1.0 mm Thick• 0.1 mm Kaption (400%) 0.4 mm• 0.15 mm S-Grass Fiber Tape (400%) 0.6 mm (include voltage tap)


Conductor Parameter IC (Inner Coil) CICC : (3SC)x4x5x6[360 SC strand], VF = 27.62% MC (Middle Coil) CICC : (2SC+1Cu)x3x4x6[144 SC strand], VF =

26.96% OC (Outer Coil) CICC : (1SC+2Cu)x3x4x6[72 SC strand], VF =

26.96% Strand : High Jc (> 2600A/mm2) Nb3Sn (total ~ 6.5 ton) Twist Pitch : 50 mm – 110 mm – 170 mm – 290 mm No Sub-Cable Wrapping

30.01.0 3.0

16.0

R 3

MC CICC Cross-section

14.0

37.0 1.0 3.0

18.0

R 3

IC CICC Cross-section

16.0

OC CICC Cross-section29

.0 1.0 2.5

15.0

R 3

13.0


Coil Parameters Peak Field in Each Coil

• IC : 16.39 Tesla, MC : 13.6 Tesla, OC : 7.9 Tesla Number of Turns per Layer

• IC : 6 turns, MC : 16 turns, OC : 13 turns Number of Layers

• IC : 20 layers, MC : 24 layers, OC : 24 layers Geometry (Excluding Ground Wrapping)

• IC : ID = 500 mm, OD = 608 mm, Height = 740 mm• MC : ID = 648 mm, OD = 904 mm, Height = 720 mm• OC : ID = 944 mm, OD = 1139 mm, Height = 696 mm

Helium Channel Length• IC : 42 m, MC : 78 m, OC : 85 m

Required SC Strand Mass : total 5,615 kg in Coil• Strand Diameter : 0.82 mm including 0.002 mm Cr Plating• IC : 1.51 ton (437 m x 2), MC : 2.66 ton (644 m x 3 x 2), OC : 1.45 ton (700 m

x 3 x 2) • Strand Required including Cabling Loss : ~6.5 ton


SUCCEX Magnet Cross-Section (Upper Coil)

70 m

m

810

mm

790

mm

766

mm

500 mm

608 mm

648 mm

904 mm

944 mm

1139 mm


Magnetic Field Profile

preliminary conceptual design study of k-demo

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