Energy Physics Engineering

Advanced Fusion Reactor Engineering
Prof. HASHIZUME Hidetoshi, Assoc. Prof. ITO Satoshi, Assoc. Prof. EBARA Shinji,Senior Assist. Prof. CHENG Weiying, Assist. Prof. SHISHIDO Hiroki
We are studying on novel technologies for designing advanced fusion reactors, from a viewpoint of integrated
energy engineering using fluid dynamics, heat transfer engineering, electromagnetics and structural mechanics.
Official Website：https://web.tohoku.ac.jp/hashizume_fan_club/home/e-home.html
If you need further information, please contact Assist. Prof. Shishido (hiroki.shishido.a7＠tohoku.ac.jp).

Designing advanced fusion reactors !
Remountable high-temperature superconducting magnet• Design of mechanical andcooling structures

Superconducting
poloidal coil

Huge and complex superconducting magnet for a fusion reactor
Remountable high-temperature superconducting (HTS) magnet

Advantage：Easy fabrication, High maintainability
Important features for a commercial fusion reactor !

Superconducting
helical coil
• Fabrication of a prototype magnet
BlanketCryostat
Vacuum vessel
Supportstructure

Schematic illustration of a remountable HTS magnet• R&D in mechanical joints• R&D in HTS conductors• R&D in porous channel for
local heat removal

Remountable Coil Bobbin

ステンレスSS jacket
ジャケット

Jointing Region

接合Joint

ダイバータ
Divertor

Core plasma

Helical fusion reactor, FFHR-d1(National Institute for Fusion Science)

4 Jointing Regions
高温超伝導テープ線材
HTS tape

High current HTS conductor(100 kA at 4.2 K for 1 hour)

Divertor cooling technique

100 kA
Voltage Tap

銅ジャケットCu jacket

5-Layered BSCCO 2223 Cable

Experiment for heat transfer
enhancement of liquid nitrogen

Mechanical bridge joint

Prototype of a remountable HTS magnet

Ultra high heat flux at the divertor
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

Advanced liquid blanket Advantage: Flibe or liquid lithium can play a role as a tritium breeder and coolant
Liquid Lithium / Vanadium alloy channel blanket:

Molten salt Flibe blanket:• R&D in new molten salt to be suited for heat removal
and tritium breeding• Design of a blanket system having a function of
nuclear transmutation of a spent fuel• Reduction of MHD pressure drop by a three-surfacemulti-layered channel• Evaluation of thermo-fluid characteristic for Li/V blanket

Firstelbow

Fabrication of a
prototype channel
Frame 001  04 Jan 2013 

3D dual elbow tube
2nd out

Secondelbow
3D dual elbow tube
for flow field visualization

HFLSM, IMR, Tohoku University
2.1

0.2

[m/s]

Reynolds shear stressdownstream of elbow tube

2nd inSwirling flow at outletof a dual elbow tube

UCLA
R&D in new molten
salt based on MD

Evaluations of cooling and nuclear characteristics for a
Flibe blanket having a function of nuclear transmutation

Applying the technique

MHD simulation

Heat removal experiment using
arc plasma with high heat flux

MHD flow experiment byusing high field facilities

Nondestructive testing/evaluation for component of a fusion reactor• R&D in structural inspection techniques using various NDTs
- 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

Incident

欠陥部
DefectApplying the technique• R&D in a crack radar (Microwave NDT)

マイクロ波
Oscillator
発振部
マイクロ波
Wave（入射波）

Microwave can propagate rapidly in a pipe
Microwave is reflected at defect inside a pipe

We can scan defects rapidly withthe microwave NDT technique!

マイクロ波
Reflected（反射波）
wave

Microwave NDT for a elbow pipe

NDT for a joint of a remountable HTS magnet using X-ray CT

Microwave NDT for a long pipe

Experimental data to predict
locations of wall thinningElectromagnetic simulation for microwave NDT(Axial component of electric field)

Research Topics
Design and development of a remountable high-temperature superconducting magnetDesign and development of advanced liquid blankets
Development of a divertor cooling technique using self-formed flow field
Development of nondestructive testing/evaluation methods for component of a fusion reactor
Development of a system to transmute radioactive wastes using fusion neutrons