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Energy Physics EngineeringAdvanced Fusion Reactor EngineeringCourse of Quantum Science and Energy Engineering, Department of Mechanical and Aerospace Engineering
Prof. Hidetoshi Hashizume, Assoc. Prof. Noritaka Yusa, Assoc. Prof. Satoshi Ito, Assis. Prof. Jing Wang
Designing advanced fusion reactors !!
We are studying on novel technologies for designing advanced fusion reactors, from aview point of integrated energy engineering using fluid dynamics, heat transfer engineering,electromagnetics and structural mechanics.
Designing advanced fusion reactors !!
ダイバータ
Remountable high-temperature superconducting magnet
R&D in HTS conductors
Advantage:Easy fabrication, High maintainabilityImportant features for a commercial fusion reactor !
Huge and complex superconducting magnet for a fusion reactorRemountable high-temperature superconducting (HTS) magnet
Remountable Coil BobbinRemountable Coil Bobbin
R&D in porous channel for local heat removal Fabrication of a prototype magnet
R&D in mechanical joints
Design of mechanical and cooling structures
Schematic illustration of a remountable HTS magnet
CryostatVacuum vessel
Supportstructure
Divertor
Superconductingpoloidal coil
Core plasma
Superconductinghelical coil
Blanket
H li l f i t FFHR d1
Divertor cooling technique
Cooling technique using self-formed flow field R&D in divertor cooling technique using
self-formed flow field in elbow tube basedon flow field visualization and heat removal experiments
Prototype of a remountable HTS magnetHigh current HTS conductor(100 kA at 4.2 K for 1 hour)
4 Jointing Regions
5-Layered BSCCO 2223 Cable
Voltage Tap
Jointing Region
5-Layered BSCCO 2223 Cable
Voltage Tap
Jointing Region
Experiment for heat transfer enhancement of liquid nitrogen
100 kA
接合
高温超伝導テープ線材銅ジャケット
ステンレスジャケット
Mechanical bridge joint
Advanced liquid blanket Molten salt Flibe blanket: R&D in new molten salt to be suited for heat removal
d t iti b di
Advantage: Flibe or liquid lithium can play a role as a tritium breeder and coolantLiquid Lithium / Vanadium alloy channel blanket:
Reduction of MHD pressure drop by a three-surface-multi-layered channel
Ultra high heat flux at the divertor
Helical fusion reactor, FFHR-d1(National Institute for Fusion Science)
HTS tape Cu jacket
SS jacket
Joint
2.1
0.2
[m/s]
2nd in
2nd out
Swirling flow at outlet of a dual elbow tube
3D dual elbow tube3D dual elbow tube
for flow field visualization
Reynolds shear stress downstream of elbow tube
and tritium breeding Design of a blanket system having a function of
nuclear transmutation of a spent fuel
Evaluation of thermo-fluid characteristic for Li/V blanket
Circular MHD Flow Channel Magnet (Bmax=5.5T)
Fabrication of a prototype channel
UCLA
HFLSM, IMR, Tohoku University
First elbow
Secondelbow
Nondestructive testing/evaluation for component of a fusion reactor
Microwave can propagate rapidly in a pipeMicrowave is reflected at defect inside a pipe
We can scan defects rapidly with the microwave NDT technique!
マイクロ波(入射波)
マイクロ波発振部
欠陥部
マイクロ波(反射波)
of a dual elbow tube
Heat removal experiment using arc plasma with high heat flux
R&D in a crack radar (Microwave NDT) R&D in structural inspection techniques using various NDTs
Microwave NDT for a elbow pipe
- Radiation: X-ray CT, X-ray transmission method- Ultrasonic wave: Harmonic ultrasonic wave testing- Electromagnetics: DC/AC electric potential technique,
Eddy current testing, Magnetic detection
Evaluations of cooling and nuclear characteristics for a Flibe blanket having a function of nuclear transmutation
R&D in new molten salt based on MD MHD simulation
MHD flow experiment by using high field facilities
UCLA
Applying the techniqueApplying the technique
Incident Wave
Reflected wave
Defect
Oscillator
Research topics
Experimental data to predict locations of wall thinning
Electromagnetic simulation for microwave NDT(Axial component of electric field)NDT for a joint of a remountable HTS magnet using X-ray CT Microwave NDT for a long pipe
Hashizume/Yusa/Ito Laboratory's website: http://afre.qse.tohoku.ac.jp/
Design and development of a remountable high-temperature superconducting magnetDesign and development of advanced liquid blanketsDevelopment of a divertor cooling technique using self-formed flow fieldDevelopment of Nondestructive testings/evaluations for component of a fusion reactor