Chinese Fusion Energy Strategy

J. Li, Institute of Plasma Physics, CASOutline

Ø Introduction
Ø Progresses and activities of CFETRØ Future PlanØ SummaryTop Priorities of CN-MCF

Ü Make ITER successful
Ü Promoting Domestic MCF
Ü Build CFETR when it is readyCN MCF Roadmap
1 GW, Power
Plant Validation

II：DEMO validation, Q>10, CW, 1 GW, >50 dpa
I：Q=1-5, steady state, TBR>1, >200MW, <10 dpa
Phase I I：Q=5, 3000 s, 350 MW, steady-state burning plasma
Phase I ：Q=10, 400 s, 500 MW, Hybrid burning plasma
Advance PFC, steady-state advanced operation
Advanced divertor, high power H&CD, diagnostics
Disruption mitigation, basic plasma
2015

2020

2025

2030

2035

2040

2045

2050

2055

2060

Tokamak Experiments
EAST
30MW H&CD
80 Diagnostics
W-divertor
10MW/m2
Long pulse
AD SSO

Outcome:500 SCI papers
5 PRL
50 NF
40 Invite talks
200 PhD
300 Master

HL-2A 15MW, 50 diagnostics

HL-2M 25MW, 60 diagnostics

J-TEXT, 20 diagnostics

CFETR mission
Obtained
Burning Plasma
for fusion power

Steady-state operation
for fusion energy

1. P=200-1500MW

2. Q=1-10，SSO， hours

3. Q=20-30 hours-SSO
4. High energetic α heating
5. Hybrid（OH+BS+CD）

6. SSO（ Ext H&CD +Higher fb）

7. PSI on the first wall
8. Heat&particle exhaust on Div.

T-breeding by blanket
10. T-plant: extract & reprocessing
11. Materials&components
12. Reliable and quick RH
13. Licensing&safety
9.

Breeding
Breeding Tritium
for T self-sustained
self-sustainedforStrategy of CFETR-centralized teamNew design version
The key points changed:
Larger size:
R= 7-7.5m(5.7),
a=2-2.5m(1.6)
Higher BT: 5.0-7.0 T (5)Advanced CS magnet:≥ 480 VSLower Ip: 6-12MA
16 TF coils for easy RH, H&CD
More reliable Plasma targets
Higher confidence for STE goals

New version of design(7m, 6.5-7T)

New version of design(7m, 6.5-7T)
H/He: 1-2 years
DD:
1-2 years
DT< 100MW：1 years
DT ：200MW, 5 years
SSO, T fuel cycle
DT ：500MW
SSO, TBR>1, 3 years
DEMO validation：
DT 1GW，5 years
Advance Scenario：>1.5GW , Q~30
2-3 years
Total: 15-20 years

CFETR Physics design (SSO)
0D system code + 1.5D integrated modeling(OMFIT, EFIT, ONETWO, GATO,TGYRO/TGLF, NEO,ELITE)
Off-aix NBI + ECCD, EC+LHCD are major H&CD
tools together with bootstrap current for SSO
Using 800 kV NBI( 1.1MA/10MW) +190GHz ECCD
for early phase operation.

16 TF Coil design (High Performance Nb3Sn)

Parameters for TF magnet
Parameters
strandCoil 1

Coil 2high Jc(2700A/mm2) Nb3Sn
Φ1.0mm strand

No. of SC strand

1350

270

Turns66

154

Operating current for
Bt=7.0T
Bmax in coil
Max Force58kA
15.5T

11.4T
760MPaCS Model Coil –Nb3Sn (baseline)
Coil Parameters
Design Parameters of CFETR CS Model CoilMax. field

12 T

Max. field rate

1.5 T/s

Inner radius

750 mmCoil structure

Hybrid magnet
Inner：Nb3Sn coilConductor type

Nb3Sn CICC

13Start experiments @ 2017.12 in new ASIPP site （Huainan)CS Model Coil (1/3 size) – 2212 CICC (Target)
Max.240 v.s

Max.20 T

Conservative：enhanced Nb3Sn: 360VS 4-6h
Ideal：2212CICC，2x480VS，~8h ( for Ip=13MA)

wirecable

Batch production for 200-m long Ф1.0mm wires
4.2K, 14T: Jce > 750A/mm2，ITER~ 320A/mm2。
4.2K, 20T: Jce > 660A/mm2，ITER ~ 200A/mm2。
high pressure sintering process is on the way,
Jc-B property may be increased for 3 times.

Bi2212-High temperature Superconducting Central solenoid

CS coils include eight Bi2212 coils. Each coilconsists of 14 double pancake

conductor

Water cooled ceramic breeder blanket design
Main features

Material sectionØØØØ

Mixed breeder of Li2TiO3 and Be12Ti
A bit of Be to improve neutrons multiplying.
RAFM steel as structural material.
Tungsten as armor material of the FW

For Phase-I

Coolant : 15.5MPa, 285 oC inlet/325 oC outlet
The cooling plates and the breeder zone parallel to the FW
The compact coolant enlarges the breeder zone.
Purge gas is directed in the toroidal direction to reduce its
pressure drop.

4 (Rad.)×4 (Tor.) mixed breeder zones and 2 (Rad.)×4 (Tor.) thin Be layers

Module structure

For Phase-IIØØØØTemp. distribution

Neutron flux
distribution

TBR: 1.21

Tritium production rate
(PF0.8, 6Li80% case)

8 (Rad.)×4 (Tor.) mixed breeder zones and 2 (Rad.)×4 (Tor.) thin Be layers

TBR: 1.1

Shielding capability for TFC
ItemLimits

Module radial building

Temp. distribution along radial
direction

value

Fast neutron (>0.1MeV)
fluence in TFC conductor(n/cm2)

1×10193.67×1016

Fast neutron (>0.1MeV) fluenceinTFC insulator (n/cm2)

5×1017

1.10×1017

Nuclear heating rate in TFC
case(W/cm3)
Nuclear heating rate in TFC
conductor (W/cm3)

2×10-3

2.19×10-5

1×10-3

1.88×10-5Helium cooled ceramic breeder blanket design
Material sectionØØØØ

Main features

Li4SiO4 as tritium breeder
Be as neutron multiplier.
RAFM steel as structural material.
Tungsten as armor material of the FW

For Phase-I

Ø Modularized breeding unit
Ø Multi-layer back plates manifold

Coolant : 8 MPa, 300 oC inlet/500 oC outlet

5 (Tor.)×2 (Pol.) breeding unit, each has one U-shape breeder unit.

Stress analysis

Typical module structure

For Phase-II

TBR: 1.213

6 (Tor.)×5 (Pol.) breeding unit, each has two U-shape breeder unit.

Typical module structure

Modularized breeding unit

Temp. distribution

TBR: 1.15

New Divertor validation
56603@3.0s

EAST- SF

2PF9PF7PF111.5

CFETR- XPF51PF13PF3IC10.5

Z [m]

PF10

PF2-0.5

IC2PF4PF14-1PF6-1.5

PF12PF8PF10-20.5

11.52R [m]2.53

H98>1.1,ne/nGW=1.1-1.3,Vp=0, 1/15 heat load

Physics: field expansion + radiation; Reduce the heat detailsimulations（5y）+ experimental validation (5-8y）Engineering：design & manufacture of key components
W mono-block: >20MW/m2
W-Cu mono-block：> 20MW/m2 （5-10y）
Inner+external coils optimization is underway up 15MA （12MA）

R&D for Divertor Target
Monoblock W/Cu
5000 cycles at 10MW/m2Efforts for 30MW/m2

300 cycles at 20MW/m2.

Flat tile W/Cu

3D printing full W block: Tw=1700C

Flat tile
5000 cycles
at 10MW/m2

1000 cycles
at 20MW/m2

W/ODS-Cu
Tw = 1650C
Tcu = 520C

Tritium cycling systems (T-plant )l 3 main loops for tritium recovery:Ø Inner cycling：- Tritium recovery, isotopic separation from plasma
exhaust gases and re-fueling to torus.

Ø Outer cycling：- Tritium extraction and measurement from in thefull breeding blanket.

Ø Tritium confinement and effluent detritiation.
l Main parameters for tritium process flow

(4500s of time span for cycling):

Ø Inner cycling: ~357g T/shot, 2m3（D2,T2)/hfor TEP and SDS, >4m3/h for ISS .
Ø Outer cycling: tritium extraction every twoweeks to get more than 200g of pure tritiumfrom the breeders.
Ø Tritium confinement: 3g/a of enviromental
tritium release at current stage, to beminimized as 0.6 g/a for the future.
l Key technologies development for eachsub-system are in progress

Simple block diagram of CFETR tritium plant

In-Pile Tritium Release and Extraction Test
Maximum load 500 g
Tritium production1 Ci/day
Online refueling, irradiation
Irradiation temperature 300-750 ℃
Neutron flux ~5×1013n cm-2s-1

Maximum load 400 g
Tritium production1 Ci/day
Online thermal conductivity test
Irradiation temperature 400～850 ℃
Neutron flux ~5×1013n cm-2s-1

China Mianyang Research Reactor

China Advanced Research Reactor

R&D on VV 1/8 mock-up

17.4m

NG-TIG system

Welding samples

Laser Tracker Measurement on VV Sector

Overview of CFETR VV Design

R&D of Narrow Gap TIG Welding on VV

Test bench for installation ,replacement ofVV components by RH

Assembly of VV Poloidal Sectors

RH—Starts from design

EAST AIA(CEA)VV
Integration Lab.of RH

Roadmap of materials
2020

2030s

2040

FW: W，W alloy

3-5dpa10dpa, CFETR

20dpa, CFETR

Advavced W

1E25-1E28 PSI

CFETR

CFETR

10dpa

50dpa, CFETR

100dpa, CFETR

Low active FS

5dpa, 1000T

50dpa, CFETR

100dpa, CFETR

ODS-LFS

10dpa，kg

50dpa，CFETR

100dpa，CFETR

Li4SiO4

specification，T level

fix，CFETR

CFETR

Li2TiO3

specification，T level

Fix，CFETR

CFETR

Fission reactor

fix，CFETR

CFETR

500C，1000

500C，1E4，CFETR

500C，1E5，CFETR

Divertor
ODS-Cu， Cu alloy
Structure Material

Breeding Material

Neutron multiplier
Be12Ti

Resistance tritium layer

Materials Research Activities(Simulation, manufacture, validation)
p Low Activation Martesitic steel§ Nominal compositions: 9Cr1.5W0.2V0.15Ta0.45Mn0.1C§ 5 ton smelting with good control of main compositions

p Irradiation properties and TBM Fabrication§

HIP(0.8x1.8m)

400kW EM facility

High-dose neutron irradiation experiments( Spallation source ~20dpa )( High Fluence Engineering Test Reactor ~2dpa )§Fabrication of test blanket module (TBM)( 1/3 scale P91 TBM, 1/3 scale CLAM first wall )15kW laser welding (0.05mm)

p Plasma-facing materials: W

W material study scope: W alloy; W coating; W/Cu component

Conventional Powder Metallurgy Samples: High Purity W, W-TiC(Chemical vapor deposition) CVD-W

W-TiC

High Purity W

Deposition rate: 0.2-1mm/h
Relative density :
1#

2#

3#

4#

94.8% 95.1% 94.5% 94%

rolling direction

rollingdirecti
on

W/Cu
W/FGM-W/Cu

SPS Samples: Pure W, W-TiC, W-La2O3
W/OFHC-Cu

W/graphite

High heat-flux
test facility

Pure W Φ80×10mm

W-TiC Φ80×10mm

W/RAFM SteelMaterial testing neutron sources
The Materials Irradiation Facility in China(CMIF)

TargetHigh Neutron Flux
Low Neutron Yield
Small Sample Size
~1MW granular Be/C Target

Beam

50~100MeV@(5~30)mA (CW)

Cost

Lowenergy（MeV） 20

BISOL ProjectII
I

50

Flux(D+Be)

3.6*1013

2*1014

Y (n·cm-2·mA-1·s-1)*5 mA*10 mA

Flux(D+Be)

9.81*1014

2*1015

Y (n·cm-2·mA-1·s-1)*20mA*30 mA

Hefei DT 14Mev：1-5X1012 now
CMIF 6-20MeV：2X1014-2X1015

2020

Experiments validation(EAST+DIII-D)

Bottom Divertor：CFETR–like, 20MW/m2, AD configuration
4MW CW 170GHz EC, new ICRF, HFLHCD(7.5GHz)

1、Q=1,100MW，L-mode ， hybrid or Steady state
2、Q=3, 200MW，H（betaN =1.9,H=1.2, fbs50%)， hybrid or SSO
3、Q=10,500MW，H（betaN =3, H=1.2, fbs60%)， hybrid or SSO
26
4、Q=20,1500MW，H（betaN =3,H=1.5, fbs80%)， hybrid or SSO

CFETR 5 years Plan– Detail design + Large scale R&D

CFETR Detail Engineering design starts (30M$)
1. Physics design (14 tasks)
2. Nuclear design (16 tasks)
3. Tokamak detail engineering design (64 tasks)
4. Aux. Detail functional design (18 tasks)
5. Database IDM (6 tasks)
Fully Open to international cooperators
T-Plant + Plasma exhaust + breeding Blanket

CFETR 5 years Plan--Large scale R&DBlanket:
small size mockup(14MeV),
thermal hydraulic Testing Full size, water & He gas configurations
Magnets:
full size CICC Nb3Sn(TF), Nb3Al (PF), Bi 2212 Conductor (CS)CS mockup coil, 1/6Nb3Sn, 1：1 prototype Nb3Sn TF, small 2212 CSGyrotron:
10s 1MW , 140GHz, 170GHz,
design 230GHz

CFETR 5 years Plan--Large scale R&D
NNBI: -200keV, 3600s,
ECRH: full size 4MW,ICRF: 2MW, full size
LHCD: 4.6GHz, 2MW, High field PAM
RH: Vertical + MPD
Assembling testing facility: installation and RH
Larger SC testing facility (CICC conductor, CS, proto type TF)
Experimental verification(8): EAST
SS L mode, SS H-mode, Hybrid long pulse… with diagnosis,
control, divertor, up to 1000s 10keV

Education—Training next generation tenants
10 scientists + 10 engineers/year, 0.5M$/person 4 yearsÜEncourage to join EAST, HL-2A experimentsÜEncourage to join Th&SimulationÜEncourage to join CFETRÜBasic plasma scienceÜFusion engineering and technology

More than 30 top universities

Education—Training next generation tenants
清华SUNIST

等离子体所HPPX

哈工大FLARE

大学Helimak

SUNIST
中国科大KTX

等离子体所HT-7

中国科大LMP

工物院氚渗透装置

北航STEP

浙大直线等离子体装置

兰州化物所LEPS

31 中国科大KMAX

International cooperation
Ø More than 30 years cooperation with USA
7 US-CN workshop, T&sim., Exp., Engineering, CFETR
Ø 20 years cooperation with EU
Joint workshop, exp., Engineering, joint lab.
Ø 20 years cooperation with Japan
CUP(10+5 years), A3, CN-JP-KO DAs, >1000papersØ 10 years cooperation with KO
A3, CN-KO DAs, , CN-JP-KO Das
Ø Good cooperation with RF, IN

Summary
CN-MCF development has made significant progresses
during the past decade.
EAST will play a key role for advanced steady-state operation
during next decade.
CN makes our best efforts for ITER success.
CFTER engineering design starts and large scale R&D will
start before the end of this years.
It is hoped that the proposal for CFETR construction can beapproved by government within next 5 years .

Thanks！