Introduction of National Institute for Fusion Science (NIFS) Takeo - PowerPoint PPT Presentation

MoD-PMI 2019 18, June 2019 Introduction of National Institute for Fusion Science (NIFS) Takeo Muroga Deputy Director General National Institute for Fusion Science 1

NIFS Overview ○ Es Established hed i in May, 1 1989 a 9 as an In Interuni univer ersity R Resea earch In ch Institut ute f e for promoting ng collaborations ns with J Japanes nese Univer ersities es f for plasma s science a ence and i its applica cation. n. ( (30 th th anni nniversary cel celebration ca carried o out ut in n May 2019 2019) ○ Large Hel elical D Dev evice ( (LHD) w was co cons nstructed a and nd ha has b been een o oper erated a as t the he co core e facilit ility a and a activit ity o of NIFS. ○ Present ently L LHD Project ct, N Numerica cal S Simul ulation R n React ctor R Resea earch ch Proj roject, F Fusion on En Engineer neering ng Research ch Proj roject, and international c col ollabora ration on a are re p prom romot oted. Statistics in 2018 Entrance Entrance • Organization structure ▫ 126 researchers, 45 engineers & technicians, 42 administration staff ▫ 53 graduate students ▫ about 100 of contract employees Budgetary condition • ▫ 8,456million yen which includes salary, operational costs of LHD Building LHD Building LHD, Supercomputer and other facilities ▫ 4,100million yen for LHD operation Collaboration programs • ▫ 538 subjects have been approved as collaborative researches in three collaboration programs

Fusion Research Activities in Japan for FY 2018 National Institute for Quantum and Radiological Science and Technology (QST) Naka-site JT-60SA Tokamak National Institute for Quantum and Radiological 6 Science and Technology (QST) Rokkasho-site IFMIF-EVEDA • 12 6 17 58 16 17 22 NIFS LHD Total numbers of universities and research institutes under collaboration with NIFS: 154 3

International collaborations Agreements representing the Japanese government ・ 6 bilateral agreements (with Australia, China, EU, Korea, Russia, USA) ・ 3 multilateral agreements (IEA-Technology Collaboration Programms) J/US J/China J/Korea Int. Base Human exchange man Day man day man day man day by leading programs to NIFS/Japan 81 360 7 61 45 163 6 71 in 2017 from NIFS/Japan 71 777 41 258 34 157 18 166 Max-Planck IPP(Germany) Peter the Great St. Petersburg Polytechnic Univ.(Russia) ● ● GPI (Russia) FOM Inst. (Netherlands) ● Kurchatov Inst.(Russia) ● ● ● KIT(Germany) ● ● FZU (Czech) ● ● CNRS ● Wisconsin Univ. Madison IPPLM(Poland) Peking Univ.(China) CIEMAT ● ● Marseile Univ ● PPPL(USA) NFRI (Korea) (USA) ASIPP (Spain) ● CEA ● ● ORNL(USA) Kharikov Inst. ● UCLA (China) ● ● IFS, Texas Univ. Austin (France) ● (Ukraine) (USA) ● ● RFX SWJTU ● (USA) SWIP(China) ● IGI (China) ● Chiang Mai Univ.(Thailand) (Italia) ● TINT(Thailand) ● ITER Academic exchange agreement Lead standard database with 29 institutes in fusion science • Confinement physics database • Promotion of collaboration and joint work • Atomic-molecular database • Human resource development/education ● Australian Nat. Univ. 4 (Australia)

NIFS carries out three projects by promoting collaboration with universities • Large Helical Device Project pursuits to achieve highest performance plasma in Heliotron configuration ▫ Enhancement of plasma parameters toward reactor relevant regime ▫ Heating, diagnostics, closed divertors, PWI and other technological progress ▫ Physics of 3-D plasma and isotope effects Numerical Simulation Reactor Research Project develops • numerical simulation methods as the basis of numerical research for helical reactors ▫ Understanding and systemizing physical mechanisms in fusion plasmas ▫ Development of theoretical models for plasma behaviors and their validation ▫ Integration of predictive models in a whole machine range Fusion Engineering Research Project proceeds fusion engineering • research to solve key issues of the helical demo reactor ▫ Development of superconducting magnet, blanket, low activation materials, divertor / plasma facing components, and tritium control system ▫ Helical reactor design studies Collaboration among the three projects are highly promoted 5

NIFS carries out three projects by promoting collaboration with universities • Large Helical Device Project pursuits to achieve highest performance plasma in Heliotron configuration ▫ Enhancement of plasma parameters toward reactor relevant regime ▫ Heating, diagnostics, closed divertors, PWI and other technological progress ▫ Physics of 3-D plasma and isotope effects Numerical Simulation Reactor Research Project develops • numerical simulation methods as the basis of numerical research for helical reactors ▫ Understanding and systemizing physical mechanisms in fusion plasmas ▫ Development of theoretical models for plasma behaviors and their validation ▫ Integration of predictive models in a whole machine range Fusion Engineering Research Project proceeds fusion engineering • research to solve key issues of the helical demo reactor ▫ Development of superconducting magnet, blanket, low activation materials, divertor / plasma facing components, and tritium control system ▫ Helical reactor design studies 6

Large Helical Device ( ＬＨＤ ) One of the world largest helical devices Height: ~ 9 m Diameter: ~ 13 m Mass: ~ 1500 t Experiment started in March 1998 Inner view of vacuum vessel

LHD has proceeded to the new research phase Deuterium experiment started in March 2017 and will last 9 years 8

Status Report from LHD Deuterium experiment (2017~) has extended LHD operational regime  Fusion-relevant T i = 10 keV was first Fusion triple product achieved in stellarator/heliotron (by courtesy of M. Kikuchi) 9

Initial growth phase of the W-fuzz structure was observed in the LHD  Total time ： 10190s (22 shot of He) Cross-sectional TEM  Surface temp.: 1500K-2300K image  Incident He energy: ~100 eV  He flux : ~5 × 10 21 He/m 2 s  He fluence ： ~5 × 10 25 He/m 2 Material probe system IR camera W 20nm (80x30x1.5mm 3 ) SEM image Plasma The finest initial growth phase of the fuzz structure 100nm (divertor strike point) M. Tokitani et al., Nuclear Materials and Energy 12 (2017) 1358–1362 10

Exhaust Behavior and Mass Balance of Tritium Exhaust detritiation system with precise detector revealed tritium behavior in LHD (2017) 1 10 10 Tritium inventory in LHD Tritium exhaust rate: 35.5 % of produced tritium Exhausted tritium 8 10 9 35.5 % was exhausted until the Tritium amount [Bq] end of the first D-campaign, 6 10 9 and 64 % was still retained in vacuum vessel or Tritium exhaust rate: 4 10 9 5.1 % evacuation system Out of the retained tritium, 2 10 9 half is stored in the divertor plates 0 17/3/12 17/4/9 17/5/7 17/6/4 17/7/2 17/7/30 Mass balance of tritium during the first deuterium experimental campaign from March 6 to August 7 11

Next Stage of LHD – Steady State Operation Present Large Tokamak machine LHD JT-60S 60SA (QST) T) Near future ITER machine Next Stage of LHD Plasma sustainment 10 4 1 10 1000 100 (sec) Fuel cycling, impurity transfer Erosion and deposition of walls Diffusion and microstructural evolution of wall materials Short time scale Mass/particle balance MHD Current diffusion ・ W cycle and impact on plasma Energy/particle Long time scale Wave/particle ・ Multi-scale interactions confinement interaction Particle and energy cycle Atomic/molecular processes Plasma-wall interaction is the critical issue for the steady state operation 12

NIFS carries out three projects by promoting collaboration with universities • Large Helical Device Project pursuits to achieve highest performance plasma in Heliotron configuration ▫ Enhancement of plasma parameters toward reactor relevant regime ▫ Heating, diagnostics, closed divertors, PWI and other technological progress ▫ Physics of 3-D plasma and isotope effects Numerical Simulation Reactor Research Project develops • numerical simulation methods as the basis of numerical research for helical reactors ▫ Understanding and systemizing physical mechanisms in fusion plasmas ▫ Development of theoretical models for plasma behaviors and their validation ▫ Integration of predictive models in a whole machine range Fusion Engineering Research Project proceeds fusion • engineering research to solve key issues of the helical demo reactor ▫ Development of superconducting magnet, blanket, low activation materials, divertor / plasma facing components, and tritium control system ▫ Helical reactor design studies 13

Extensive simulation code developments and comparisons between simulation and experiments towards numerical helical test reactor Neoclassical transport Turbulent transport Edge plasma (EMC3- (FORTEC-3D) (GKV-X) EIRENE) Plasma-wall interaction High energy particle (MEGA) (MD-MC) Non-linear MHD Integrated transport code VR visualization (MINOS,MIPS,NORM) (TASK3D) 14