Present Status of CFETR

Transcription

1 Welcome to USTC

2 Present Status of CFETR Presented by Yuanxi Wan 1, 2 1 University of Science and Technology of China, Hefei, China 2 Institute of Plasma Physics, CAS, Hefei, China wanyx@ipp.ac.cn or wanyx@ustc.edu.cn May 11-15, th IAEA DEMO Workshop,Hefei, China

3 Content Road Map of MFE in China Present Status of CFETR Summary

4 Roadmap of MFE development in China Background China is facing serious energy problem now and future Burning plasma has been achieved on JET,TFTR, (JT-60) Some progress of MF research has been achieved before China join ITER project Government made big decision to join ITER project Significant progress of MF research has been achieved since China join ITER project

5 Roadmap of MFE development in China A national integration design group for CFETR was founded by MOST at 2011 The progress on the conceptual design and some R&D of CFETR has been achieved A special group for drafting the MF roadmap in China has been organized by MOST According to the draft roadmap it is hoped the proposal for CFETR construction can be approved soon 5

6 The Road Map of MFE development in China ( the first draft ) by the roadmap draft group 6

7 Roadmap for Chinese MFE Development (~2050) (~2021) (2030 start operation) 1GWe, Power Plant Validation I:Q=1-5, steady state, TBR>1, >200MW, 10dpa II:DEMO validation, Q>10, CW, 1GW, 50dpa Phase I :Q=10, 400s, 500MW, Hybrid burning plasma Phase I I:Q=5, 3000s, 350MW, steady-state burning plasma Advance PFC, steady-state advanced operation Advanced divertor, high power H&CD, diagnostics Disruption mitigation, basic plasma

8 Milestones of the Roadmap : Join and fully support the construction, operation and experiments of ITER; enhance the support for pre-experiments on EAST, HL-2M and J-TEXT; : Start to construct the Chinese Fusion Engineering Testing Reactor (CFETR) : Complete the construction of CFETR ( P f ~200MW and test of SSO and tritium self-sustained ) : Complete the upgrade of CFETR ( P f ~1 GW, Q eng > 1 ) : Complete the construction of Prototype Fusion Power Plant (PFPP) (~1GWe, Power Plant Validation) 8

9 Technical Route adopted by the Roadmap By superconducting-tokamak and bootstrap current plus the external CD to achieve the SS burning plasma operation By the efficient breeding blanket and advanced tritium factory technology to achieve the Tritium self-sustained.

10 The main challenges 1. To achieve and sustain the high performance burning plasma to be SSO or long pulse with high duty cycle time in fusion reactor; 2. Tritium should be self sustainable by blanket and high efficient T- plant; 3. The materials of first wall and blanket should have suitable live time under the high heat load and fusion neutron flux irradiation ; 4. High Efficient electricity generation on fusion reactor ( Q eng > 1 ) 5. Reliability, RH, Nuclear Safety and Environmental Impact ( License ); 6. Overall Integrated design of fusion reactor. 10

11 Content Road Map of MFE in China Present Status of CFETR Summary

12 Present Status of CFETR The Conceptual Design of CFETR has been completed; R&D activities of CFETR are in progress Further working plan:

13 Progress of CFETR Conceptual Design

14 National Integration Design group for Magnetic Confinement Fusion Reactor has been founded Tasks: 1. learn from ITER 2. Design of CFETR 3. Cultivating talented people for MFR 4. Any others if needed,

15 Thanks to all of supporters Since the national design group was founded at 2011: 11 group and 2 international workshops have been held and more than 100 design ( research) reports have been provided. More than 150 physicists, engineers and 100 graduated students work for CFETR The group has always got strong support by USTC, ASIPP, SWIP, CAEP, HUST, and international fusion community. 15

16 核科学技术学院核科学技术学院 CFETR Conceptual Design I p =7-10 MA B to = T R 0 = 5.7 m ; a = 1.6 m; k=a/b=1.8~ 2.0 q 95 3; β N ~2-3 P fusion : 200MW~1GW Possible upgrade to R~5.9 m, a~2 m, B t = 5T, I p ~14 MA

17 The Conceptual Design is included in 1. Layout design and system Integration 2. Plasma physics and technology 3. Superconducting magnet and cryogenics 4. Vacuum vessel & vacuum system 5. In-vessel components: - blanket & diverter 6. Heating & Current Drive system 7. Diagnosis & CODAC 8. Electrical power & control system 9. Fuel circulation system & waste disposal 10. Radiation protection & safety, RAMI 11. Remote control and maintenance system 12. Auxiliary supporting system 13. Project management

18 The most advanced design and 3D simulation platform has been set up Design and management servers Terminals of the design cloud Virtual reality system Remote handling Magnet Cryostat Divertor Blanket Vacuum Vessel

19 Advanced features of the design platform on the internet storage 3D-CFETR.wmv

20 Roadmap for Chinese MFE Development (~2050) (~2021) (2030 start operation) 1GWe, Power Plant Validation I:Q=1-5, steady state, TBR>1, >200MW, 10dpa II:DEMO validation, Q>10, CW, 1GW, 50dpa Phase I :Q=10, 400s, 500MW, Hybrid burning plasma Phase I I:Q=5, 3000s, 350MW, steady-state burning plasma Advance PFC, steady-state advanced operation Advanced divertor, high power H&CD, diagnostics Disruption mitigation, basic plasma

21 Key parameter investigation Operation ITER Upgrade A B C D E mode -SS I p (MA) P aux (MW) ~ q W(MJ) 171~ ~ P Fus (MW) 197~ ~ ~ Q pl 3.0~ ~ ~ T i0 (kev) 17.8~ ~ ~ N el (10 20 /m 3 ) n GR N 1.59~ ~ T (%) ~ ~ f bs (%) 31.7~ ~ Y2 (s) 1.82~ ~ P N /A(MW/m 2 ) 0.35~ ~ I CD (MA) 3.0~ H T burning (S) 1250 SS 2200 M/SS SS?? ThPO-3 B. Wan, etc.

22 By V. Chan

23 By V. Chan

24 By V. Chan

25 CFETR Magnet System Parameter ITER-Like Super-X Snowflake ITER Number of TF coils Plasma current(ma) Central magnetic field(t) Maximum current of TF coil (ka/turn) Major radius(m) Minor radius(m) Ohm field coil center radius(m) Maximum Volt second Elongation 1.8/ / / /1.85 Number of PF coils Front U-shaped Back U-shaped structure structure Front inner panel CS3U CS2U Tightening Tie Plate block The magnetic flux distribution. The maximum B of CS coil is about 12 T Back inner panel Toroidal flexible support CS1U CS1L CS2L CS3L Z (m) The maximum of stray field in plasma area is stray field from about 2GS to 14 20GS GS Bottom support structure R (m)

26 CFETR Vacuum Vessel - A torus shaped double wall structure; - To provide high vacuum for plasma and primary radiation confinement boundary; - To support in-vessel components - Important space of the Vacuum Vessel for plasma; - First safety barrier; The vacuum vessel: 4 upper ports 8 equatorial ports 8 lower ports. Upper port Inner-shell These ports are used for equipment installation, vacuum pumping, maintenance, etc. Equatorial port Lower port Outer-shell T-ribs

27 CFETR Blanket

28 CFETR Divertor Snowflake divertor design Three configurations: ITER-Like, Snowflake and Super X. New structure with vertical reflector : inner baffle, inner particle reflector, inner target, dome, outer target, out particle reflector and outer baffle. Cassette structure for easier RH handling. Shared cassette between snowflake and ITER-like divertor. Small incident angle ~16. Closed V shape configuration. Pumping gap between dome and targets. Divertor cooling scheme was developed. Support design compatible with RH was finished.

29 CFETR tokamak assembling

30 CFETR blanket with the RH

31 CFETR site (1)

32 CFETR site (2) 1. physics investigation 2. Tokamak reactor integrated desing 3. H&CD 4. CODAC 5. Daignostics 6. SC magnets

33 CFETR Conceptual Design has been summarized

34 Preparation of the further experiments on EAST, HL-2A and J-TEXT

35 Roadmap for Chinese MFE Development (~2050) (~2021) (2030 start operation) 1GWe, Power Plant Validation I:Q=1-5, steady state, TBR>1, >200MW, 10dpa II:DEMO validation, Q>10, CW, 1GW, 50dpa Phase I :Q=10, 400s, 500MW, Hybrid burning plasma Phase I I:Q=5, 3000s, 350MW, steady-state burning plasma Advance PFC, steady-state advanced operation Advanced divertor, high power H&CD, diagnostics Disruption mitigation, basic plasma

36 Two sets of RMP coils Static RMP: Outside of VV Consist of 5 coils Rotating RMP: Inside VV 12 saddle coils to generate static or rotating RMPs J-TEXT tokamak in HUST

37 HL-2A is upgrading to HL-2M

38 EAST: ITER/CFETR pre-experiments

39 H & CD capabilities on EAST allow truly advanced SS operations NBI-2 LHCD : 10MW 2014: 26MW 2016:26+8MW ICRH-1 ICRH-2 NBI-1 ECRH-1 LHCD-1 ITER-like RF-dominant H&CD, capable to address key issues of high performance SS operations

40 Progress of CFETR R&D via ITER CN PA Superconducting Technologies: Strands; Cabling, Jacketing and so on; Coil winding and magnets: PF6, CC, EML; Feeders; Power supply and control system: AC/DC converter Blanket: SB,TBM

41 Progresses of CN PA also for CFETR R&D by Western Superconducting Technologies Co., Ltd.

42 Progresses of CN PA also for CFETR R&D Progress of Conductor PA 3 jacketing lines and conductor integrating facility were set up in ASIPP. 2 parallel buildings were set up for conductor integrating, NDE, cabling, acceptance test. All conductors produced by CN DA were accepted with their first tests. The first ITER oversized components, PF5 conductor, arrived at ITER site in June. 900m CICC jacket line Conductor fabrication process Ceremony for 1st shipping TF conductor arriving Italia TF conductor arriving PF conductor arriving ITER site Japan

43 Overview of Feeder system in ITER Progresses of CN PA also for CFETR R&D Significant progresses of ITER HTC feeder achieved 31 Feeder systems. No two pieces are identical. >1000 tons, >tens thousands of different parts. Feeder PA is on stage II. Critical technologies were developed in ASIPP. Mock-ups will be developed before production. 72 HTS current leads (including prototypes and back-ups) will be supplied. 10/52/68kA three types current leads are designed and developed. 7 mockups were finished. PF5 in-cryostate feeder trial Verification of Busbar Current lead prototype

44 Progresses of CN PA also for CFETR R&D Progress of power supply PA: PS Test Facility can meet all ITER PS test requirement

45 Progresses for CFETR R&D by domestic program 1/16 VV mock-up 1/6 CS magnet Tritium technologies: T-Plant, Breeding material Materials : CLAM; first wall- W, neutron source RH

46 CFETR 1/16 VV mock-up Size Value Torus outside diameter 19.5m Torus inner diameter 5.74m Torus height 11.4m Shell thickness Weight Structure Welding joint 50mm 155.3*16=1242.4t Double wall Full penetration Allowable leakage Pa m3 s-1 Magnetic permeability 1.05 Welding quality ISO-5817 B CFETR VV 1/16 Sector Mock-up 真空室 1/16 模型件设计 VV Main Parameters Shell Forming Overview of CFETR VV Design Design of 1/8 Sector of VV Laser Tracker Measurement on VV Sector R&D of Narrow Gap TIG Welding on VV Assembly of VV Poloidal Sectors

47 1/32 section mock up of the CFETR VV

48 One Section(1/6) of CFETR CS Model Coil Coil Parameters Nb 3 Sn Coil Design Parameters of CFETR CS Model Coil NbTi Coil Max. field Max. field rate Inner radius Coil structure Conductor type Nb 3 Sn Conductor 12 T 1.5 T/s 750 mm Hybrid magnet Inner:Nb 3 Sn coil Outer:NbTi coil Nb 3 Sn CICC NbTi CICC NbTi Conductor 48

49 Progress of preparation of solid tritium breeder CAEP independently developed a frozen- wet preparation technology of solid tritium breeder, currently has a preparation capability of kilograms in lab. Li 4 SiO 4 pebble Li 4 SiO 4 pebble CFETR T-plant technologies Preparation level of Kg class Compressive strength(a.v.) >20 N Phase purity ~99% Tritium permeation barrier Formation of tritium permeation barrier (TPB) on vessels and pipes for tritium confinement is the first choice to minimize tritium loss and its environmental radiological risk. A series of oxides, aluminides, carbides and nitrides of TPB have been studied, and high tritium permeation reduction factor (PRF) can be obtained. TPB type Oxides Carbides and nitrides Compounds Materials Al 2 O 3,Cr 2 O 3,Er 2 O 3,(Ar,Cr) 2 O 3 TiN,TiC,SiC Al 2 O 3 /FeAl,Er 2 O 3 /SiC,SiC/TiC@Al-Cr-O Process chemical and physical process physical process chemical and physical process PRF 400~10000 > ~3000 D.Zhu, et al. J. Nucl. Mater, 2010 X. Gao, et al. J. Nucl. Mater, 2012 X. Gao, et al. J. Nucl. Mater, 2012

50 Materials research: LAM; first wall-w Production and properties Nominal compositions: 9Cr1.5W0.2V0.15Ta0.45Mn0.1C 4.5 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 ) 1/3 CLAM FW 1/3 P91 TBM 1/3 CLAM FW 1/3 P91 TBM Properties of CLAM steel is comparable with those of the other RAFMs, e.g. Eurofer97, JLF-1. W material study scope: W alloy; W coating; W/Cu component High heat-flux test facility

51 CFETR RH strategy

52 Some Achievements of RH project ~ 80%

53 RH test on EAST

54 RH test on EAST

55 Further working Plan of CFETR Start the Engineering Design of CFETR with stable funding support as soon as possible; Propose more key R&D items for CFETR Making great effort in order to the construction of CFETR can be approved before 2020; It is hoped that the construction of CFETR can be approved within next few years and CFETR can be constructed around 2030.

56 Further working Plan of CFETR Re-organize the design team by Drs. Li, Liu and Wang J.Li Y.Liu X.L.Wang Promote both domestic and international collaboration more wide on design, R&D, and construction of CFETR J.Li V.Chan CIC Director Division head of fusion plasma physics

57 Design and R&D strategy for CFETR

58 Summary The MFE roadmap is under discussion in China Integrated conceptual design of CFETR has been completed and some R & D activities are in progress The engineering design of CFETR will begin soon and more key R&D items will be planed Wide international exchange and collaboration for CFETR are welcome!

59 Thanks for your attention! 3D-CFETR.wmv Test- CFETR.wmv

60 Oral and Poster of CFETR Oral. J. LI Closing Gaps to CFETR Readiness P1. *VINCENT CHAN AND NAN SHI Development of a physics-engineering integrated platform for CFETR design P11. *Y. T. SONG CFETR design P13. CHANGLE LIU et al The Strategies and an Approach of the Shielding Blanket to CFETR Reactor P14. Y. YANG et al. Basic Requirements of Plasma Diagnostics on CFETR