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

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

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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

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Introduction of National Institute for Fusion Science (NIFS)

Takeo Muroga Deputy Director General National Institute for Fusion Science

MoD-PMI 2019 18, June 2019

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○ 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. (

(30th

th

anni nniversary cel celebration ca carried o

  • ut

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

  • per

erated a as t the he co core e facilit ility a and a activit ity o

  • f 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

  • n

En Engineer neering ng Research ch Proj roject, and international c col

  • llabora

ration

  • n a

are re p prom romot

  • ted.

NIFS Overview

Entrance Entrance LHD Building LHD Building

Statistics in 2018

  • 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, Supercomputer and other facilities ▫ 4,100million yen for LHD operation

  • Collaboration programs

▫ 538 subjects have been approved as collaborative researches in three collaboration programs

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SLIDE 3

Fusion Research Activities in Japan

NIFS LHD Total numbers of universities and research institutes under collaboration with NIFS: 154

16 17 22 6 17 58

for FY 2018

12

JT-60SA Tokamak

6

  • National Institute for Quantum and Radiological

Science and Technology (QST) Naka-site National Institute for Quantum and Radiological Science and Technology (QST) Rokkasho-site

IFMIF-EVEDA

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Agreements representing the Japanese government ・ 6 bilateral agreements (with Australia, China, EU, Korea, Russia, USA) ・ 3 multilateral agreements (IEA-Technology Collaboration Programms) Human exchange by leading programs in 2017

J/US J/China J/Korea

  • Int. Base

man Day man day man day man day to NIFS/Japan 81 360 7 61 45 163 6 71 from NIFS/Japan 71 777 41 258 34 157 18 166

International collaborations

  • PPPL(USA)

KIT(Germany) ●

  • IFS, Texas Univ. Austin

(USA)

  • ORNL(USA)

CIEMAT ● (Spain)

  • Australian Nat. Univ.

(Australia)

  • GPI (Russia)
  • Kurchatov Inst.(Russia)

ASIPP (China)

  • UCLA

(USA)

  • CNRS
  • Marseile Univ
  • CEA

(France)

  • RFX
  • IGI

(Italia)

  • ITER

FOM Inst. (Netherlands)

  • SWIP(China)

Academic exchange agreement with 29 institutes

  • Promotion of collaboration and joint work
  • Human resource development/education
  • Chiang Mai Univ.(Thailand)
  • TINT(Thailand)
  • Wisconsin Univ. Madison

(USA)

Lead standard database in fusion science

  • Confinement physics database
  • Atomic-molecular database
  • Kharikov Inst.

(Ukraine) IPPLM(Poland)

  • FZU (Czech)

SWJTU ● (China)

  • NFRI (Korea)
  • Peking Univ.(China)

Max-Planck IPP(Germany)

  • Peter the Great St. Petersburg Polytechnic Univ.(Russia)

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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

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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

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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

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Deuterium experiment started in March 2017 and will last 9 years

LHD has proceeded to the new research phase

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Status Report from LHD

Deuterium experiment (2017~) has extended LHD operational regime

 Fusion-relevant Ti = 10 keV was first achieved in stellarator/heliotron

Fusion triple product (by courtesy of M. Kikuchi)

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Plasma IR camera

W

(80x30x1.5mm3)

Initial growth phase of the W-fuzz structure was observed in the LHD Material probe system

100nm 20nm Cross-sectional TEM image SEM image The finest initial growth phase

  • f the fuzz structure

(divertor strike point)

  • M. Tokitani et al., Nuclear

Materials and Energy 12 (2017) 1358–1362

  • Total time：10190s (22 shot of He)
  • Surface temp.: 1500K-2300K
  • Incident He energy: ~100 eV
  • He flux : ~5×1021 He/m2s
  • He fluence： ~5×1025 He/m2

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2 109 4 109 6 109 8 109 1 1010 17/3/12 17/4/9 17/5/7 17/6/4 17/7/2 17/7/30 Tritium amount [Bq] Tritium exhaust rate: 35.5 % Tritium inventory in LHD Exhausted tritium Tritium exhaust rate: 5.1 %

Mass balance of tritium during the first deuterium experimental campaign from March 6 to August 7

Exhaust Behavior and Mass Balance of Tritium

Exhaust detritiation system with precise detector revealed tritium behavior in LHD (2017)

35.5 % of produced tritium was exhausted until the end of the first D-campaign, and 64 % was still retained in vacuum vessel or evacuation system Out of the retained tritium, half is stored in the divertor plates

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Next Stage of LHD – Steady State Operation

Fuel cycling, impurity transfer Diffusion and microstructural evolution of wall materials Mass/particle balance

1 10 100 1000 104

Long time scale

Next Stage of LHD

JT-60S 60SA (QST) T)

Present machine Near future machine

LHD

Large Tokamak ITER

MHD Energy/particle confinement Current diffusion Wave/particle interaction Atomic/molecular processes

Short time scale

Erosion and deposition of walls ・W cycle and impact on plasma ・Multi-scale interactions

Particle and energy cycle

Plasma sustainment (sec)

Plasma-wall interaction is the critical issue for the steady state operation 12

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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

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Turbulent transport (GKV-X) Non-linear MHD (MINOS,MIPS,NORM) Edge plasma (EMC3- EIRENE) Neoclassical transport (FORTEC-3D) VR visualization Plasma-wall interaction (MD-MC) High energy particle (MEGA) Integrated transport code (TASK3D)

Extensive simulation code developments and comparisons between simulation and experiments towards numerical helical test reactor

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Fuzzy structure formation by BCA-MD-KMC multi-hybrid simulation Helium injection into polycrystalline W

Recent research activities of NSRP for PWI

BCA-MD-KMC multi-hybrid for fuzzy formation solves

  • He injection by BCA (binary collision approx.)
  • He diffusion by KMC (kinetic Monte-Carlo)
  • W deformation by MD (molecular dynamics)

Binary-collision-approximation –based simulation of helium injection into polycrystalline

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PLASMA SIMULATOR

  • Supercomputer system for numerical

simulation research at NIFS (“Plasma Simulator”) was replaced by Fujitsu PRIMEHPC FX100 with the total peak performance about 2.62 Petaflops, and the total main memory about 81TB in 2015. (Right): Snapshot of present plasma simulator, FX100, ( peak speed: ~2.62PF, memory: ~81TB, period: 2015-2019) (Left): Peak performances of plasma simulator and numbers of submitted jobs per month in the second mid-term period

2500 5000 7500

5,837 7,561 4,608 1,795 1,629 1,517 901 902 944 2009 2010 2011 2012 2013 2014 2015 2016 2017

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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

17

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Research Roadmap of FERP

2019 Engineering design of fusion reactors

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Operation point is explored using systems code “HELIOSCOPE” based on “Direct Profile Extrapolation (DPE)” from LHD experiment data Fusion Gain of 15 was demonstrated

Helical reactor FFHR design integration

Innovative ideas have been integrated (1) to overcome difficulties with 3D structure (2) to enhance passive safety (3) to improve plant efficiency 19

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Facilities Installed into NIFS for Collaboration with Universities

These allows characterizations

  • f the specimens

exposed to D-D plasma of LHD

PWI, PFC

  • riented facilities

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“ACT- 2” 300 kW Electron Beam for Divertor Testing

Divertor mock-ups (upper: small, lower: large) fabricated by bonding tungsten plates to ODS-Cu block using advanced blazing technique/ (W/BNi-6/GlidCop) The small divertor test sample showed heat flux resistance to 24 MW/m2 Divertor component planned to be installed into LHD

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SUMMARY

  • NIFS is an Interuniversity Research Institute promoting

collaborations mainly with Universities and international partners for plasma and fusion research.

  • Large Helical Device (LHD) is the core facility which entered

recently to D-D operation phase, and is planning to enhance steady-state operation research.

  • In addition to LHD, Numerical Simulation Reactor Research

Project and Fusion Engineering Research Project are carried out.

  • For these Project researches, Plasma-Wall Interaction is the

critically important research subject.

  • Thus, for us, collaboration with PMI Model/Data community

is crucially important.

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