Iter Tbm Ws Hasegawa

8/3/2019 Iter Tbm Ws Hasegawa

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2/17

Summary of Current Status for TBMs

WSG1 (Helium-cooled/Be (F/M steel, SiC/SiC) Blankets

- TBM of F/M steel has been proposed

- SiC/SiC Blaket: DEMO Design Study (DREAM), SiC/SiC Material Tests, Specimen

Irradiation Test, Research on Cooling, Some of them by JUPITER-II

WSG2 (Helium-cooled Lithium Lead (F/M steel, SiC/SiC) Blankets

- Demo Design Study (Vector), Many activities existed. Interesting aloso for ICF

blanket, Proposal will be made

WSG3 (Water-Cooled Ceramic/Be (F/M steel) Blankets- Demo Design Study, R&Ds on corrosion, heat transfer, material irradiation being

conducted

WSG4 (Self-Cooled Lithium (V) Blankets

- Network activities in Universities/NIFS, Evaluation of Russian Design, Going to

design Japanese Blanket, Planning of R&D, Researches on vanadium alloy,

coating, impurity control, tritium recovery, cooling, some of them by JUPITER-II and by IFMIF.

WSG5 (Self-Cooled Molten Salt Blankets)

- Network activities in Universities/NIFS, Demo Design Sudy of FFHR,

R&Ds on many parts (redox control, cooling, tritium recovery, ) some

of them by JUPITER-II, by TNT-loop, planning of R&D for TBM.


3/17

Expected ParticipantsDpt. of Quantum Science and Energy Engineering

Tohoku UniversityStructure materials : Hasegawa (Tohoku Univ.)

Kohyama( Kyoto Univ.)

Solid breeding materials : Enoeda (JAERI)

Shikama( Tohoku Univ.)

Neutron multiplier : TBD (JAERI)

Shibayama(Hokkaido Univ.)

Thermomechanis : Shimizu (Kyushu Univ.)System design : Konishi (Kyoto Univ.)

Tritium recovery system : TBD

The advanced Helium cooled blankets will be studied by

collaborative works by universities and JAERI.


4/17

Current interests in various blankets by parties

Parties JA EU US RF China Korea

PB/He

LiPb/He

Pb/Water

Li/V

Salts


5/17

Roadmap for Materials and BlanketDevelopment in Japan

Materials and Blanket System Development

Reference Material (RAFM) and System

Design Construction Operation

ITER

Power Generation Plant

Irradiation Test, Materials Qualification and System Performance TestIFMIF

1st commercial plant Design

(Staged construction and operation)

(Licencing) (Blanket test)

Blanket Module Test

Approximate calendar year 2015 2020 2030 2040

Advanced Materials (V-alloy, Flibe,SiC/SiC --) and System

Reference Blanket (Mostly JAERI responsibility)Advanced option (Mostly NIFS/University responsibility)

modification


6/17

Back Ground of this ActivitiesDpt. of Quantum Science and Energy Engineering

Tohoku University

Based on irradiation behavior of SiC, advanced SiC/SiCcomposites were developed using stoichiometric SiCfibers.

increase radiation resistance using advance fiberno mechanical degradation up to 10dpa at 800Chigh size stability

Recent achievement of SiC/SiC composites -1-


7/17

Back Ground of this ActivitiesDpt. of Quantum Science and Energy Engineering

Tohoku University

Development of new matrix processing, NITE, enabledto increase matrix density.

The lower porosity and near theoretical density realized

high hermeticity and good thermal conductivity of

SiC/SiC composites.

Joining between SiC/SiC composites was also

successful by the NITE process.

It is almost ready to fabricate complex shape structure madeof SiC/SiC composite such as gas cooling blanket .

To start design activity of the blanket system, the technical

issues will be discussed in this working group.

Recent achievement of SiC/SiC composites -2-


8/17

NITE: Nano-Infiltration Transient Eutectic Phase Process Dense and robust structures (cf. PIP, CVI, )

Fairly high thermal conductivity

Chemical stability

Thin plate production, surface smoothness, potential gas

tightness Applicability of existing net-shaping techniques

Low production cost

What is NITE Process ?

Matrix slurry;

SiC + Additives

Fabrics

Infiltration of slurry Drying

Hot pressing


9/17

Shape-Variability of NITE Composites

Tube: 31-33 x 60.0mmThin Plate: 195 x 195 x 2.0mm

Thick Block: 97 x 97 x 70mm Combustor Liner

Kohyama et al.,(2002)

Qualification of these composite is inprogress under collaboration with hightemperature gas turbine program.


10/17Hino et al.,(2003)

Monolithic SiC by NITE

SiC/SiC by NITESiC/SiC by NITE

#1 Pilot SiC/SiC by NITE (Ube )

Permeability of NITE Composites at RT


11/17

Research Areafor High Temperature Gas Blanket System

Dpt. of Quantum Science and Energy Engineering

Tohoku University

Study on blanket system design for high temperaturegas-cooling system is started in Japan to realize highefficiency energy source of fusion power plant. Design

and feasibility studies base on the following fields willbe discussed in this working group.

Material development, Thermomechanics,

Tritium recovery system

Material Design for High Temperature Blanket System

Structural Materials, Sold Breeding Materials,

Neutron Multiplier Materials


12/17

Bulk-flow typeDREAM Channel type DEMO, HCPB

Advanced Gas Cooling System

There are two types of gas cooling system

1) Bulk-flow type : one major gas loop

2) Channel type : two major gas loops

( T purge gas loop + He gas cooling loop)

Dpt. of Quantum Science and Energy Engineering

Tohoku University


13/17

Bulk-Flow Type

Heat EfficiencyBlanket

Heat Exchanger

Tritium RecoverySystem

900 DREAM

Tritium RecoveryEfficiency

High

High


14/17

Channel type

Blanket CoolingLoopTritium Recovery

Loop

900

1000

High HeatEfficiencyHigh Tritium

RecoveryEfficiency


15/17

Key issues of this Blanket SystemDpt. of Quantum Science and Energy Engineering

Tohoku UniversityTo realize high energy efficiency of blanket, highertemperature (900) outlet-gas is required.

New breeding material which has higher temperatureresistance is needed to utilize high temperature capability of

SiC/SiC composite.

ex. coating or dendrite structure breeding materials

Upper limit of current solid breeding materials :


16/17

SumaryDpt. of Quantum Science and Energy Engineering

Tohoku University

In the high temperature gas cooling system, manymaterial and system issues remain and some break-through of high temperature resistance of breedingmaterial are required.

Japan proposes to include testing of SiC/SiCcomposite and high temperature blanket concepts inTBMs.

Considering about limited resources andtimeframe, this advanced blanket module is expectedto join later phase of ITER.


17/17

TitleDpt. of Quantum Science and Energy Engineering

Tohoku University

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Iter Tbm Ws Hasegawa