Overview of the Present Progresses andActivities on the Chinese Fusion
Engineering Test Reactor

Y.X. Wan 1,4, J. Li 1, Y. Liu 2，X.L.Wang3, and CFETR Team
1) Institute of Plasma Physics, CAS, Hefei, China
2) Southwest Institute of Physics, Chengdu, China
3) Chinese Academy of Physics Engineering, Mianyang, China
4) University of Science and Technology of China, Hefei, China

26th IAEA Fusion Energy Conference, Kyoto, Japan 17–22 October 2016

Outline

OV/3-4¾ Introduction• CN MCF Roadmap• Mission of CFETR¾ Progresses and activities of CFETR• Previous concept design• New design version•

Phase I•

Phase II

¾ Key R&D activities¾ Summary- 2-CN MCF Roadmap

1 GW, PowerPlant 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
20152020

2025

2030

2035

2040

2045

2050

2055

2060- 3-

Mission & Objectives of CFETR
Mission: Bridge gaps between ITER and DEMO,
realization of fusion energy application in Chinaz

A good complementarities with ITERz

Rely on the existing ITER physical （k~1.8, q>3, H~1) and technical(SC magnets, diagnostic, H&CD) baseszDemonstration of the burning plasma with Pf = 200MW~1000MWz

Demonstration Long pulse or steady-state operation of burning withduty cycle ≥ 0.3 ~ 0.5z

Demonstration of full cycle of T self-sustained with TBR over 1.0z

Exploring options for DEMO blanket & divertor with an easychangeable core by RHz

Exploring the technical solution for licensing DEMOz

With power plant potential step-by-step approach.
- 4-Outline

OV/3-4¾ Introduction• CN MCF Roadmap• Mission of CFETR¾ Progresses and activities of CFETR• Previous concept design• New design version•Phase I•

Phase II

¾ Key R&D activities¾ Summary- 5-The advanced design and 3D
simulation platform has been set up

Terminals of the design cloud

Design and management servers

MagnetRemote handling

Cryostat

Virtual reality system

DivertorBlanket

Vacuum Vessel- 6-

Advanced features of the design platform

on the internetstorage- 7-

First Design version of CFETR (2011.11-2015.8)
Phase I
• Ip=7-10 MA• Bto = 4.5-5.0T• R0 = 5.7 m ;• a = 1.6 m;• k=1.8～2.0• q 95 ≥ 3；
• βN ～2-3
Pfusion : 200MW
Phase II
Possible upgrade
to R~5.9m, a~2.0m, Bt= 4.8 T,
Ip~15MA
Pfusion : 1000MW- 8-

核科学技术学院
Key parameter investigation (180VS）
核科学技术学院

Operation
Amode
Ip(MA)
10Paux(MW)65q95
3.9W(MJ)
171~174
PFus (MW)
197~230
Qpl3.0~3.5
Ti0(keV)
17.8~18.5
Nel(1020/m3)
0.75
nGR
0.6
1.59~1.62
βN~2.0βT(%)
fbs(%)
31.7~32.3
1.82~1.74
τ98Y2(s)PN/A(MW/m2) 0.35~0.41
ICD(MA)
3.0~3.1
H98
1
Tburning(S)
1250

B
1065
3.9
193
209
3.2
29
0.52
0.42
1. S8
2.3
35.8
1.55
0.37
7.0
1.3
SS

ITER Upgra
-SSde
10
88915
65
65~70
65
59
65
3.9
4.9
4.9
5.2
3.9
270~278171
255 287540468~553 187~210 409 356 1000
7.2~8.5
2.7~3.2
6.3
6.01519.8~20.8 20.6~21211925
1.06
0.65
0.94
10.85
0.65
0.95 0.82 0.85
2.51~2.59
2
2.97 3.0
2.7
3.1~3.25
2
2.97 2.8
4.250~51.5
50
73.9
48
47
1.57~1.47
1.37
1.29 1.94 1.88
0.98
0.33~0.37 0.73 0.5
1.38
2.45
4.0
2.76
3.0
1.2
1.2
1.5 1.57
1.2
1200
2200
SS
S
C

D

Bt=4.5T; R=5.7 m; a=1.6 m; k=1.8 ~2.0

E

Bt=4.8T;
R=5.9 m; a=2.0 m;

The first design version has been summarized- 10 -

Outline

OV/3-4¾ Introduction• CN MCF Roadmap• Mission of CFETR¾ Progresses and activities of CFETR• Previous concept design• New design version•Phase I•

Phase II

¾ Key R&D activities¾ Summary- 11 -Key issues for CFETR mission
ObtainedBurning Plasmafor fusion power

1. Lager device (Bt Ro, a
2. Standard H mode
3. AdvancedK)

operation scenario

4. Increasing flux to sustain

Steady-state operationfor fusion energy

longer Ip
5. CW Ext H&CD (NB,EC,LH,IC)
6. Higher fb
7. Higher energetic α heating
8. Divertor physics and tech.
T-breeding by blanket
10. T-plant: extract & reprocessing
11. Materials
12. RH
13. licensing
9.

Breeding Tritium
for T self-sustained- 12 -

New design version (2015.8-2016.8)
Easy transfer from Phase I to Phase II
The key points changed:
Larger size:
R= 6.7m, a=1.95m
Higher BT: 5.0-7.0 T
Advanced CS magnet:≥ 480 VS
Lower Ip: 6-12MA
12 TF coils for easy RH, H&CD
More reliable Plasma targets
Higher confidence for STEgoals- 13 -CFETR Physics design
0D system code + 1.5D integrated modeling(OMFIT, EFT, ONETWO, GATO,TGYRO/TGLF, NEO,ELITE)
Off-aix NBI + ECCD, LHCD are major H&CD tools
together with bootstrap current for SSO
Using 800 kV NBI( 1.1MA/10MW) +190GHz ECCD
for phase I operation.

- 14 -More effective current drive –HFS LHCD+Top ECCDLFS

HFS LHCDTOP ECCD
ΔI = 0.3MA
I CD=4.0MA

HFS

ILH=1.43MA

ILH=1.83MA

f=4.6GHz
P=30MW
N//=1.8

f=4.6GHz
P=30MW
N//=1.8

LFS LHCDLFS ECCD
ΔI = 0.34MA
I CD=2.49MA- 15 -Two New Fully Non-Inductive CFETR Scenarioswith Larger Size Have Been Evaluated• Computed with self-consistent core-pedetal-equilibrium model under OMFITby GA-CFETR team- 16-

New Larger CFETR Reduces Heating and Current Drive
Requirements, and Lower Divertor and Wall Power Loading
CFETR

PreviousNew•Fully non-inductive CFETR scenarios have been developed with aself-consistent core-pedestal-equilibrium model•New larger CFETR reduces heating and current drive requirements,
lower divertor heat flux and neutron wall loading, higher bootstrap
current fraction and H98y2 at similar βN•Higher βN~3.2 Phase II configuration requires a close conducting wallfor n = 1,2 ideal stability but for Phase I dont need the conducting wallby GA-CFETR team- 17 -12 TF Coil design (High Performance Nb3Sn)
conductor for coil 1

conductor for coil 2

coil 1

cablecoil 213370

coil casejacket9183

insulation

177

130888coil 2

2200
2637
2860
3105

Parameters
strandcoil 1
764

22.5°

130

Parameters for TF magnet

10595
10665
10910

3175

Coil 1

Coil 2high Jc(3000A/mm2) Nb3Sn
Φ1.0mm strand

No. of SC strand

1350

270

Turns

66

154

Operating current forBt=7.5T

11131

Bmax in coil

11383

Max Force

64.3kA
14.3T

11.4T643MPa- 18 -

Advanced plasma equilibrium shape

Ip=11 MA

Ip=14 MA- 19-

Helium cooled ceramic breeder blanket design
Material section¾¾¾¾Main features

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

For Phase-I¾ Modularized breeding unit
¾ 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.

Typical module structure

For Phase-II

Stress analysis

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

Typical module structure

Modularized breeding unit

TBR: 1.213

Temp. distribution

TBR: 1.15- 20 -Water cooled ceramic breeder blanket design
Main features

Material section¾¾¾¾

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-II¾¾¾¾Temp. 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 radialdirection

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- 21 -Tritium cycling systems (T-plant )z 3 main loops for tritium recovery:¾ Inner cycling：‐ Tritium recovery, isotopic separation from plasma
exhaust gases and re-fueling to torus.

¾ Outer cycling：‐ Tritium extraction and measurement from in thefull breeding blanket.

¾ Tritium confinement and effluent detritiation.
z Main parameters for tritium process flow

(4500s of time span for cycling):¾ Inner cycling: ~357g T/shot, 2m3（D2,T2)/hfor TEP and SDS, >4m3/h for ISS .
¾ Outer cycling: tritium extraction every twoweeks to get more than 200g of pure tritiumfrom the breeders.
¾ Tritium confinement: 3g/a of enviromental
tritium release at current stage, to beminimized as 0.6 g/a for the future.

Simple block diagram of CFETR tritium plantz Key technologies development for eachsub-system are in progress- 22 -

RH strategy of CFETR
RH strategy plays the key role for the CFETR’s high efficiency and reliability maintenance.
The vertical port maintenance scheme with multi-module segment blanket and divertor
was preferred for in-vessel components maintenance. It will make the RH simpler and more
efficient.

Top corridor and crane

Maintenance CASK

Maintenance RHBlanket radial remove RH

Transfer cask system

Assembly hallRH system cell

Hot cell
Tokamak Building

Toroidal remove RH

Hot cell RH

The vertical port maintenance scheme for in vessel components- 23 -

New Design version of CFETR

37m

34m

DC1

DC2Dimensions of CFETR- 24 -

Outline

OV/3-4¾ Introduction• CN MCF Roadmap• Mission of CFETR¾ Progresses and activities of CFETR• Previous concept design• New design version•Phase I•

Phase II

¾ Key R&D activities¾ Summary- 25 -

R&D strategy of CFETR
MoreR&D- 26 -Other important R&D for CFETR
Auxiliary Heating & CD:
9 Off-aix NBI (0.8MeV) + ECRH (top，190，230GHz)
9 LHCD（HF，4.6GHz）+ECRH (top，230GHz）

Advanced Superconducting Magnet
TF (Nb3Sn, 7.0 T); CS （Bi 2212 CICC)

Advanced Divertor (X-Divertor, >20MW/m2)
Blanket （He gas, water cooled）
T-Plant （99.9% T recovery）
Materials （First wall, structure ）RH- 27 -

R&D for RF Sources
LHW:
EAST: 2.45GHz, 200kW, CW
4.6 GHz, 0.3MW,CW
CFETR: 4.6 GHz, 0.3-0.5MW,CW
7.5GHz, 0.5MW, CW

2.45GHz, 200kW

4.6 GHz, 0.3MW

140GHz, 1MW, CWEC:
EAST: 140GHz, 1MW, CW
170GHz, 1MW, CW

5x8 hours testing for Klystrons

CFETR: 170GHz, 1MW, CW
230GHz, 1MW, CW

Gyrotron: Start commissioning @ 2016.12- 28 -

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 coil

Conductor type

Nb3Sn CICC

29Start experiments @ 2017.12 in new ASIPP site （Huainan)- 29 -CS Model Coil (1/3 size) – 2212 CICC (Target)

Max.240 v.s

Max.20 TConservative：enhanced Nb3Sn: 360VS 4-6h
Ideal：2212CICC，480VS，~8h ( for Ip=10MA)

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- 30 -New Divertor validation
EAST- SF

CFETR- X

Joint Exp.with ENEA

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）- 31-

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

Efforts 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 = 1650CTcu = 520C- 32 -

CFETR T-plant technologies- 33 -

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 - 34 -Materials Research Activities(Simulation, manufacture, validation)
 Low Activation Martesitic steel
Nominal compositions: 9Cr1.5W0.2V0.15Ta0.45Mn0.1C

5 ton smelting with good control of main compositions

 Irradiation properties and TBM Fabrication
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 )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

rollingdirection

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- 35-

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 RHAssembly of VV Poloidal Sectors - 36 -CFETR 5 years Plan
Self-consistent, reliable physical design (V.Chan)
Detailed engineering design (main machine and auxiliarysystems)
R & D for some key technologies and systems(I): Blanket related to nuclear, thermal hydraulic processes(II): magnets、T- factories、NBI、ECRH、RH(III): Experimental verification, diagnosis, control, divertor,
cryogenic, ICRF, radiation protection, assembly and so on.

- 37 -Further working Plan of CFETR
Re-organize the design team by Drs. Li, Liu and WangJ.LiY.LiuX.L.Wang

Promote both domestic and international
collaboration more wide on design, R&D, andconstruction of CFETR

J.Li“CIC” Director

V.ChanDivision head offusion plasma physics- 38 -International cooperation¾ PPPL -CFETR team, H. Nielson, T.Bown, P.Titus,
C.Kessel, A. Khodak.
¾ GA-CFETR team, L. Lao, R. Boivin, J. Candy, X. Chen,
R. Prater, M.Christopher, A. Garofalo, O. Meneghini,
M. Vanzeeland, P.B. Snyder, S.P.Smith, G.M. Staebler,E.J. Strait, and D. Zhao
¾ Useful discussion and suggestion from CFETR -IAC,
CFETR Physics group IAC¾ EU-DEMO team：（CCFE：SYScode, ENEA: Blanket,Julich: Diagnostic&Control, CCFE: RH, EPFL: H&CD,ENEA: Divertor, Julich: FM materials)- 39 -Summary
Integrated Design and R&D of CFETR are inprogress
CFETR is moving to Phase II design of the newversion with emphasis for high BT option
There are gaps to CFETR readiness, especially forphase II， need new solution and technologies.
Detail engineering design and large scale R&D willcontinue in next 5 years.
It is hoped that the proposal for CFETR construction
can be approved by government within next 5 years
finally- 40 -End and Thanks！

26th IAEA Fusion Energy Conference, Kyoto, Japan 17–22 October 2016