Recent progress of the R&D and design for high temperature …aries.ucsd.edu/LIB/MEETINGS/1203-USJ-PPS/Konishi.pdf · 2012. 3. 9. · High Plasma Q not required 1018 1022 1021 1020

S. Konishi, K.Ibano, F. Okino, K. Noborio,

T. Shibata, Y. Yamamoto and R. Kasada

Kyoto University

Recent progress of the R&D and design for

high temperature blanket and

biomass hybrid concept

Japan-US Workshop on

Fusion Power Plants and Related Advanced Technologies

UC San Diego, La Jolla,

Mar. 8, 2012

Background Kyoto University pursues the Biomass Hybrid concept from

various aspects.

Particular interest is on Socio-Economics and possible

scenario for early introduction of Fusion, with minimal

extrapolation of the current technology.

Safety, environment and the adoptation to the future

energy system are our current concern.

Contents - LiPb blanket and tritium recovery / SiC study

- zero-carbon electricity system with Micro DC grid.

- Tritium in the environment

Introduction Institute of Advanced Energy, Kyoto University

High Plasma Q not required

18 10

10 22

10 21

10 20

10 19

1 10 100

Ｔ（ｋｅｖ）

Break-even

Ｑ＝１，η＝１

Electricity

generation

Ｑ＝20，

ηe＝0.33

biofuel

Ｑ＝５，

ηｆ＝２．７

-0.6

Negative power

ITER

DEMO

Driven and pulsed

operation is acceptable

High temperature blanket

To be developed.

High output temperature is

required for gasification

efficiency is required

Biomass Hybrid Concept

Net

6Pf

Net

8Pf

Institute of Advanced Energy, Kyoto University

GNOME

4

Droplet and Diffusion

2 2 2

2 21

6 11 exp /t

n

MDn t

M n

a

droplet diameter is a

key factor for

optimum design of

the extraction system

Institute of Sustainable Science Institute of Advanced Energy, Kyoto University

5

A: Tritium balance study

To explicate the recovery

rate of Biomass Gasification

fusion reactor GNOME

B: Tentative observation of droplet

formation

from 1mm dia. nozzle by an

experimental setup (one point data )


Development of Vacuum Sieve Tray

Rp=5.2m Gasificationreactor

Pn ~1MW/m2

Hydrogen

Fuel

≧900oCHigh temp.

extraction

High η

IHX

Tritium Balance in plant

biomass

HEX

Tritium

4.5E - 04

LiPb Pb

Recovery System 1

Tritium Recovery System 2

Reactor Plasma

2.3 E - 8 2.5 E - 10

-

0.724 m 3 /s 0.652 m 3 /s

Permeation

Recovery

Consumption Blanket

4. 7 E - 04

Generation Permeation

IHX

Tritium

4.5E - 04

Pb

Recovery System 1

Tritium Recovery System 2

Reactor Plasma

T Recovered tritium

2.3 E - 8

2.3E- 08

2.5 E - 10

4.7E- 04

0.724 m 3 /s 0.652 m 3 /s

Permeation Consumption

Stock

2.3 E - 0 5 Stock

Stock

2.3 E - 0 5 Stock

[mol/s] Recovery

Blanket

4. 7 E - 04

Generation Permeation

IHX permeability , tritium confinement of

Entire power plant needs maturity and

Demonstration for social understanding.

Net TBR 1.05

n

T3-OS14

Yamamoto

Environ-mental release


Φ＝4mm

+

+

0 2

2 2

2 2 4

) 1 2 ( exp[

) 1 2 (

8 1

j

t

l

D j

j M

M

] t

depth＝√Ｄ

Ｔ２

ＬｉＰｂ

Blanket

IHX

Φ＝4.6 ｍ

H = 1.2m

at 500oC

Vacuum Sieve Tray

Vac.

Recovery ratio 45％

reruirement

Tritium in hydrogen

product

Inventory control

[mol] ：gas release M（ｔ）

[mol] ：dissolved tas M∞

D ｔ

[m]

[m2 s-1]

[ｓ] ：time

：radius of the droplet r0

：diffusion coefficient

[m] ：depth l

Tritium Recovery Process

2mm

30mm

1

exp[ 6

1 n

t

2 r

D

M

M 2 2 n ]

t 2 2 n


Tritium Recovery Process T

ritiu

m c

on

ce

ntr

atio

n in

pro

du

ct h

yd

rog

en

(B

q/m

3)

Regulation for HTO

Tritium permeability through

IHX [mol Pa-1/2 s-1 m-1]

0 0.2 0.4 0.6 0.8 1 10 1

10 2

10 3

10 4

10 5

10 6

Tritium recovery ratio[-]

10 -14

10 -15

10 -13

SiC fiber

35%

Target recovery ratio >35% in the LiPb stream

Natural background

-Recovery ratio determined from the contamination of product.

-Requirement is a function of permeability through IHX

assumed


9

Water (H2O) vs. Liquid Pb-17Li

Density Visco-

sity

Surface

tension

Temp

eratu

re

Velo

city

Length Reynolds

number

Froude

number

Weber

number

ρ[Kg/m3] μ[Pa·sec]

σ[N/m] T(C) V[m/sec]

L[m] ρUL/μ U2/gL ρU2 L/σ

H2O 1.0E+3 1.0E-3 0.07 20 3 1.0E-3 3.0E+3 9.2E+2 1.3E+2

Pb-

17Li

9.7E+3 1.5E-3 0.45 400 3 1.0E-3 1.9E+4 9.2E+2 2.0E+2

Pb-

17Li

9.6E+3 1.2E-3 0.44 500 3 1.0E-3 2.5E+4 9.2E+2 2.0E+2

Boundary equilibrium equation s

m

n S Fluid-1

Fluid-2 C

H2O & Pb-17Li

Both Surface tension regime material

1 2 1

' ' 'd

p zFr Re We

+ + n E' n n


10

Deducing formula

0L d L

q dt q

cosr a kz +

2

2 20 1

2U s s a k

a

12

2021

21

V

dVT

I kaa

kaI ka

Energy minimum by

Euler-Lagrange-Equation


11

01.89dropletd D

0

qta e

Deducing formula

Fastest grow rate at

ka=0.6970 overwhelm


12

Experimental Result

droplet dia. vs. nozzle


13

Liquid metal Pb-17Li droplet

A: Theoretically deduced droplet size formula is

B: Effective range is less than ϕ2.2mm

Both good accordance with the experimental

results and well applicable for extraction system

design engineering

What is achieved in this study

01.89dropletd D


SiC/SiC cooling panel

SiC cooling panel

・Actively cooled SiC

panel to control

heat transfer

・isolate outer RAFM

vessel structure

・obtain high

temperature LiPb

for heat


Blanket parameters

Heat flux to the FW 0.2 MW/m2

Neutron flux from the plasma 0.5 MW/m2

Boundary temperature at the

LiPb/SiC interface

1000 oC

He temperature at F82H

channel

350 oC

He temperature at SiC

channel

850 oC

Heat transfer coefficient of He

coolant at F82H channel

10000 W m-2 K-1

Heat transfer coefficient of He

coolant at SiC channel

7000 W m-2 K-1

Thermal conductivity of F82H 33.3 W m-1 K-1

Thermal conductivity of SiC 20 W m-1 K-1

複雑形状の接合 Fabrication R&D for SiC cooling panels Institute of Advanced Energy, Kyoto University

LiPb circulated >900゜C

SiC module

Installed in 900 ゜ C vessel

IHX heat transfer from LiPb to He

Loop operated >900 ゜ C

Only in the test vessel

ヒーティングコイル

アルミナ管


LiPb/He dual coolant loop

ＥＭＰ

T

T

Dump

tank

T

T

T

Gas

Chromato-

graph

hygro

meter

cooler

heater

GC

T

Primary loop

Secondary loop

Expansion

tank

P

F

F

P

MS

B Zr

GC

T

T

economizer

heater

９００℃

９００℃ ７００℃

７００℃

～200℃

SiC

tube

IHX

module

Test vessel

T

Test

section1

Test

section2

Test

section3


In CVD SiC,

diffusion in grain

boundary weems

major path.

In Hexoloy(a),

diffusion in bulk

Is regarded as

major path.

D2

D2

D2 D2

D2

D2

0.75 0.80 0.85 0.90 0.95 1.00 1.05 1.10 1.1510-18

10-17

10-16

10-15

10-14

10-13

10-12

10-11

10-10

10-9

10-8

perm

eation

(mol/

sec)

1000/T (1/K)

Permeation

experiment

Diffusion experiment

d

pA

p

SDn

h

s

▼CVD SiC

(permeation experiment)

○CVD SiC [This work]


◀Hexoloy


◆α SiC powder

(solution diffusion experiment) ▲β SiC fiber

(solution diffusion experiment)

□CVD SiC [This work]

(solution diffusion experiment)


Hydrogen permeation through SiC

Name ITER GNOME Slim-CS CREST ARIES-

RS ARIES-

AT PPCS-A PPCS-B PPCS-C PPCS-D

Country Japan Japan Japan U.S. U.S. Euro Euro Euro Euro Group Kyoto JAERI CRIEPI ARIES ARIES

proposed

year 2010 2007 2000 1998 2000 2005 2005 2005 2005

Major radius Rp m 6.2 5.2 5.5 5.4 5.52 5.2 9.55 8.6 7.5 6.1 Minor radius a m 2 1.7 2.1 1.6 1.38 1.3 3.2 2.9 2.5 2.0 Plasma current Ip MA 15 10.4 16 12 11.32 12.8 30.5 28 20.1 14.1 Toroidal field Bt T 5.3 4.4 6 5.6 7.98 5.86 7 6.9 6 5.6 Maximum field Bmax T 11 16 12.5 16 11.1 13.1 13.2 13.6 13.4 Safety factor qy 3.6 5.3 4.3 Average temperature <Te> keV 8.9 13 17 15.4 18 22 20 16 12 Average density <ne> 1020 m-3 0.61 1.1 2.1 2.15 1.1 1.2 1.2 1.4 Improvement factor HHy2 1.4 1.3 1.37 1.2 1.2 1.3 1.2 Imporvement factor H89P 2.59 3.2 2.65 Normalized beta bN 3.1 4.3 5.5 4.8 5.4 3.5 3.4 4 4.5 Bootstrap current

fraction fBS % 45 66 83 88 45 43 63 76

Normalized density fGW 0.54 0.97 1.3 0.915 1.2 1.2 1.5 1.5

Fusion power Pfus MW

500

(700) 324 2877 2970 2170 1755 5000 3600 3410 2530

Conversion efficiency η 2 0.41 0.38 0.59 0.31 0.37 0.43 0.60

Current drive power PCD

73

(100) 60.7 83 97 81 34.6 246 270 112 71

Neutron wall load Pn

0.57

(0.8) 0.48 3.1 4.5 4 3.3 2.2 2 2.2 2.4

Energy multiplication Q 10 5.3 35 20 13.5 30 35 Structure material V & steel ferrite ferrite ferrite ferrite SiCf/SiC Support material SiCf/SiC SiCf/SiC

breeder material

solid Li2ZrO3 Lq. Li LiPb LiPb Li ortho-

silicate

w/ Be LiPb LiPb

Coolant

LiPb water water Lithium LiPb water (15

Mpa)

He (8

Mpa) LiPb LiPb

Coolant temp. oC > 900 610 1100 300 300-500 700-1100

DEMO power/tritium system

plasma blanket IHX

turbine

Heat

rejection

Tritium

recovery

Reactor hall

divertor

Fuel

cycle

detritiation

plant

detritiation

detritiation

Tritium in power system is the major issue from TBM to DEMO.

1 2

3


Blanket and tritium flow

breeder coolant Tritium

recovery

IHX Genera-

tion

Detri-

tiation

solid Water

/ He

Isotopic

/chemical

Steam

generator

Rankine Isotope

WDS

Solid gas chemical Steam

generator

Rankine

Isotope

WDS

Liquid

metal

metal physical Steam

generator

Rankine

Isotope

WDS

Liquid

metal

gas chemical g-g IHX

Brayton

metal physical hybrid

Primary coolant issue : accidental release


Source: The 2011 Pacific Coast of Tohoku Pacific Earthquake and the Seismic Damage of the NPPs, p9, Report to IAEA from NISA and JENES, 4th April, 2011

Reactor Building

(R/B)

Pressure

Containment

Vessel (PCV)

Dry Well

Spent Fuel Pool

Reactor Pressure

Vessel (RPV)

Suppression Chamber Source: http://nei.cachefly.net/static/images/BWR_illastration.jpg

In the case of BWR..

Blanket and tritium flow

breeder coolant Tritium

recovery

IHX Genera-

tion

Detri-

tiation

solid Water

/ He

Isotopic

/chemical

Steam

generator

Rankine Isotopic

WDS

Solid gas chemical Steam

generator

Rankine

Isotopic

WDS

Liquid

metal

metal physical Steam

generator

Rankine

Isotopic

WDS

Liquid

metal

gas chemical g-g IHX

Brayton

metal physical Metal-gas

IHX

hybrid

Secondary coolant issue : permeation in normal operation


SiC-He heat Exchanger

Heat exchange

element

Heat exchanger

unit

vessel

insulation

2ndary

Tubes/

connect

bellows

2ndary

He in 1mary He in

2ndary

He out

1mary

He out

1mary He in 1mary

He out

1mary

Tubes/

inlet

insulation

Heat exchange

element

2ndary

He out

2ndary

He in

2ndary He out

2ndary

Tubes


DETRITIATION

SYSTEM

BUILDING

DETRITIATION

SYSTEM

FUEL LOOP PIPING

VACUUM

VESSEL DETRITIATION

SYSTEM

TURBINE

GENERATOR HX

Tritium confinement

volume

plume

soil

plant

deposition

Ground water

Emission controlled by confinement

and active detritiation both in

Normal and accidental

Condition.

Crops vegetables

Grazing animals

dose

Contami- nation


Yearly change of tritium concentration

0.1

1

10

0 20 40 60 80 100

Operatinf time (year)

Atm

osph

ere

HTO

conc

entr

atio

n

(Bq/

m3)

0.001

0.01

0.1

1

10

100

-100 -80 -60 -40 -20 0 20 40 60 80 100

Distance from fusion plant (km, -West, +East)

Atm

osp

here

HTO

Cocentr

atio

n (B

q/m

3)

1st year 2ndyear4th year 10th year20th year 40th year60th year 80th year100th year

Change on the tritium concentration in the atmosphere

during prolonged operation is analyzed.

5.7 km west

100 km west

•Tritium concentration increase for about 60 years on land.

•Tritium concentration on the sea surface is low and dose

not show accumulation

Emission rate: 1.35x1014 Bq/year

0.01

0.1

1

0 20 40 60 80 100

Operatinf time (year)A

tmos

pher

e H

TO

conc

entr

atio

n

(Bq/

m3)

Atmosphere HTO concentration after 100 years operation.

Tutorial course

・Environmental models converts emission to dose.

・Major dose from normal operation comes from ingestion

・mSv per person, per year per 1 gram emission.

particular concern is a damage for sales of food

products.

Total tritium dose during 1 year

operation calculated by NORMTRI.

Structure of NORMTRI model

Accumulation in the environment

Acknowledge W. Raskov and D. Galeriu


1.0E-03

1.0E-02

1.0E-01

1.0E+00

0 20 40 60 80 100

Operating time (year)

Atm

osp

here

HT

O

conc. (B

q/m

3)

1.0E-04

1.0E-03

1.0E-02

1.0E-01

0 20 40 60 80 100

Operating time (year)

Atm

osp

here

HT

O

conc. (B

q/m

3)

5.7 km west

100 km west

Operating time: 1 year Operating time: 2 years Operating time: 4 years Operating time: 10years Operating time: 20 years Operating time: 40 years Operating time: 60 years Operating time:80years Operating time: 100 years

•Considerably increases for 20 years

•Still negligible from dose, but easy to detect.

- If 100 plants operated 100 years?


Accumulation in the environment

Annual emission accumulates in the environment


With accumulation, dose is still below 10 mSv/year

•However, 15 times larger than the first year.

Tritium dose: 1 year operation

Tritium dose: 100 years operation

Effects on dose Institute of Sustainable Science Institute of Advanced Energy, Kyoto University

Coastal model Inland model

Coastal siting absorbs tritium by isotopic dilution

•Inland tritium also decreases by the tritium migration

•Existence of sink prevents environmental

accumulation.

Tritium concentration distribution

Effect of open water surface Institute of Sustainable Science Institute of Advanced Energy, Kyoto University

0.1

1

10

0 20 40 60 80 100

Operatinf time (year)

Atm

osph

ere

HTO

conc

entr

atio

n

(Bq/

m3)

0.001

0.01

0.1

1

10

100

-100 -80 -60 -40 -20 0 20 40 60 80 100

Distance from fusion plant (km, -West, +East)

Atm

osp

here

HTO

Cocentr

atio

n (B

q/m

3)

1st year 2ndyear4th year 10th year20th year 40th year60th year 80th year100th year

5.7 km west

100 km west

•Inland tritium continue to accumulate until balance

with decay.

•Little accumulation observed on the coast.


0.01

0.1

1

0 20 40 60 80 100

Operatinf time (year)A

tmos

pher

e H

TO

conc

entr

atio

n

(Bq/

m3)

Atmosphere HTO concentration after 100 years operation.

Stopped accumulation Institute of Sustainable Science Institute of Advanced Energy, Kyoto University

0.01

0.1

1

10

100

1000

-100 -80 -60 -40 -20 0 20 40 60 80 100

Distance from plant (km, W-E)

Ato

mosphere

HTO

concentr

ation (

Bq/m

3)

Off shore siting is even more effective.

Emission at 5 km from the coast decreases

Atmospheric tritium to 1/10.

Coastal model Off shore model

Tritium concentration distribution

Off-shore location Institute of Sustainable Science Institute of Advanced Energy, Kyoto University

• Tritium can be well controlled but normally discharged at below

legal limits.(annual, single plant.)

• Water detritiation requires further development and significant

cost is anticipated.

• Tritium in the environment and foods can easily be detected.

• Annually controlled emission can be accumulated and spreads.

• Releases from multiple sources can be summed.

• Canadians report tritium control experience in normal operation of Heavy Water Reactors (expensive coolant with minimal

loss with reasonable efforts) to be 1000Ci/y order /unit.

→Fusion should be as clean as fission with minimal cost.

Tritium in the Environment Institute of Sustainable Science Institute of Advanced Energy, Kyoto University

Electric grid capacities

Physics Today, vol.55, No.4 (2002)

Stability of the grid is region specific.

Eastern Grid

~500GW

Texas Grid

~53GW

Western Grid

~140GW

East Japan

~80GW

West Japan

~100GW

UTPTE ~270GW

Thailand ~20GW

Vietnam ~8GW

Extremely large Grids in a country Internationally connected Grids Delicately controlled grids - these are all exceptional in the future energy market.

Electric grid is a national security issue and

cannot be easily integrated.

Physics Today, vol.55, No.4

(2002)

Fusion startup could be a problem

-0.35

-0.3

-0.25

-0.2

-0.15

-0.1

-0.05

0

0 5 10 15 20 25 30

time(sec)

frequency(H

z)23MW/sec

77MW/sec

230MW/sec

All the generators on the grids are synchronized

→ Exactly same amount generated as demanded.

Sudden increase of demand or unstable generator

• Demands exceed generation capacity

• Frequency drops (~0.1%)

• Load to the generators

• Generator disconnected

Chain reaction kills the grid.

→unstable renewables can

initiate the blackout.

Zero-carbon energy Kyoto

Frequency drop by load

Small grid, large load,

Fast change should be

Avoided.

Fire

Hydro

Nuclear

Fire(Coal)

0 6 12 18 24(h)

variable

.

• For near term, leveling of

the load is important.

• Local generators, co-

generation and batteries

preferred.

• Increased renewable

jeopardizes grid

• For future, substitute of

fire power needed.

→load leveling power

is preferred. Can fusion be a base load?

Hydro

Solar

Wind

Load

Leveling

needed

Daily Peaks

Hydro

Base

load

・unpredictable change of generating power of renewable is large

・time constant of seconds

・controlled power to compensate this change needed

・connecting to grid decreases amplitude but not time constant

・fire power can provide only slow change (~5%/min)

4:00 8:00 12:00 16:00 20:00-0.2

0.0

0.2

0.4

0.6

0.8

1.0

1.2

1.4

1.6

1.85/14 (Cloudy)―　Insolation Intensity

―　DC Power

DC

Pow

er

[kW

]

Inso

lation Int

ensi

ty [

kW/m

2]

Inso

lation Int

ensi

ty [

kW/m

2]

Time

-0.02

0.00

0.02

0.04

0.06

0.08

0.10

0.12

0.14

0.16

0.18

4/15 4/30 5/15 5/30 6/14 6/290

20406080

100120140160180200220240

Spring (4/1-6/30)

Date

Ele

ctrica

l Ene

rgy

[kW

h/da

y]

Change of solar in a day

Required Stabilizing

power

Fluctuation of renewable

Daily change of solar

Future low carbon Systems

Battery

Large scale grid

generators

Local systems

Solar cell

Fuel

Electricity must be powered by

Carbon-free sources

Nuclear

(??)

Both large grid and local

systems are needed.

Fire

(fade out)

Fusion

(to come)

PHV,EV

Battery, generators and

fuel cells Stabilizes

fluctuation by renewables.

Large scale supply of fuels for

Fuel cells needed.

Solar cell

Fuel cells

SOFC

Power

[kW]

Max.pow

er[kW]

capacity[

kWh] units area[m2] Vol.[m3]

Solar 633 566.2 - - 4740 -

battery 364.7 420 2625 7 - 16.7 Fuel cell - 988 - - - 5.6

計 998 1974 2625 7 4740 22.2

0 4 8 12 16 20 24-400

-200

0

200

400

600

800

1000

1200

Time [h]

SOFC+NaS+Solar①, Summer, Fine

Large scale grid

SOFC

NaS-2

NaS-1

Solar

Ele

ctrica

l Ene

rgy

[kW

h/h]

0 4 8 12 16 20 24-400

-200

0

200

400

600

800

1000

1200

Time [h]

SOFC+NaS+Solar①, Summer, Rain

Large scale grid

SOFC

NaS-2

NaS-1

Solar

Ele

ctrica

l Ene

rgy

[kW

h/h]

Carbon-free elcecticty systems

Future Energy Systems

FIRE

NUCLEAR

0 6 12 18 24(h)

Load

following

power

Battery

Large scale grid

FC

Fuel Cells

DC Microgrid

Solar cell

Fuel (H2 / CO)

Electricity will be powered by

Carbon-free sources

Fusion

Day peak will be supplied by

Battery and fuel cells.


AC

DC

Office

Only for startup ~ 400 MW

Fusion reactor (2 GW)

Large-scale

power generation

Day

Only night, for NaS

Office

Transport etc. 6.5 GL/day

DC Microgrid

DC Microgrid

DC Microgrid

Large scale grid

0

100

200

300

400

500

600

700

Fusion start-upCharge of NaS

Fission,Hydro

SOFC

16 20 24 4 8 12

Time [h]

Ele

ctr

ical Energ

y [

MW

h]

H2 16 GL/day

2.9 GL/day

Indirectly supplied by fusion

6.7 GL/day・104Microgrid

Fusion and grid Institute of Advanced Energy, Kyoto University

Fusion will be started by

night sources

0 5 10 15 200

5

10

15

20

25

IV-② SOFC+NaS+Solar

従量電灯B

シナリオI-IV (2025 target)

積算

コス

ト [

億円

/μ

G]

導入年数 [年]

2025cost(NEDO)

• Micro Grid can be cheaper

than large Grid for long runs.

• combination of generation

technology is needed to

stabilize the supply.

• Carbon-free system can be

made before 2050.

0 4 8 12 16 20 24-800

-400

0

400

800

1200

1600Large scale grid

NaS-2NaS-1

SOFC Solar

Time [h]

SOFC+NaS+Solar②, Summer, Fine

Ele

ctrica

l Ene

rgy

[kW

h/h]

generator [105¥/kW]

SOFC 20

Solar 12

NaS 29

Commercial electricity

Year from the introduction Cu

mula

tive c

ost [1

08¥/s

yste

m]

Cost of micro grid electricity Institute of Advanced Energy, Kyoto University

biomass hybrid from tritium aspect

○Fusion –biomass hybrid may demonstrate fusion energy

earlier than pure fusion electricity.

・small power generation has better market chance.

・cost requirements for the product (hydrogen, oil) may be

easier (eventually. Depends on oil price and carbon tax)

・fusion-fuel cell combination may be a preferred option.

○High temperature blanket/divertor are realistic challenge

・SiC-LiPb blanket being developed.

・low pressure system is preferred from safety aspects

○ Tritium self sufficiency and environmental effect is concerned.

・tritium recovery from breeder needs demonstration (TBM)

・demonstrated safety will be important to launch DEMO

・environmental tritium contamination needs social understanding.


• Fuel production from biomass continued to be

studied.

• Fukushima accident required additional consideration

for fusion safety.

• High temperature, low pressure LiPb blanket has

preferred safety features.

• Public is aware of Existing radioactive contamination.

• Energy security with renewables will be a major

concern in the future.

• Fusion needs an adequate position in the future

energy system.

Conclusion Institute of Advanced Energy, Kyoto University

Documents

Recent progress of the R&D and design for high temperature …aries.ucsd.edu/LIB/MEETINGS/1203-USJ-PPS/Konishi.pdf · 2012. 3. 9. · High Plasma Q not required 1018 1022 1021 1020