Nuclear Fusion Device

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Nuclear Fusion Device

• spica

2
Introduction
Energy rate of self-sufficiency 4
important
Nuclear Fusion Device
3
Introduction
thermal power
advantage
fault
CO2
Low cost
NOX
hydraulic power
atomic power
efficient
efficient
high cost
melt down
clean
clean
4
Amount of power generation
thermal power
hydraulic power
generating station
Effective head 110 m Volume of water 327
handred million
LNG 1 million ton
Calorie that power plant of 1 million kW class
makes in one year
atomic power
nuclear fusion
Heavy hydrogen Tritium 175kg
Condensation uranium 23 ton
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Why Nuclear fusion device?
Very high energy
Lithium
Resource exists for 10 million years or more.
NOx
CO2
Easy on the environment.
100 years later
1/1000000
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Whats the nuclear fusion reaction ?
Heavy hydrogen (D)
Neutron (n)
17.6MeV
Nuclear fusion
Tritium (T)
Helium (He)
2D3T?4He1n17.6MeV
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How is the nuclear fusion reaction caused?
1000 km/s or over
Nuclear fusion
1000 km/s or over
100 million degrees or over
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Amount of power generation
1985
ITER plan inauguration
1988
Conceptual design activity (CDA) is executed by
Japan , EU , Russia and USA.

1990
1992
Engineering design activity (EDA) is executed by
Naka (JPN) , San Diego (USA) and Girls Kinch
(Ger) .

1998
1998
Extension engineering design activity (EDA) is
executed by Naka (JPN) and Girls Kinch (Ger) .

2001
Engineering design activity ends. The site
selection work by an official inter-governmental
conference begins.
2001
The construction site is decided to Cadarache
(France) .
2005
The ITER international nuclear fusion energy
mechanism starts.
2007
Central temperature (million ?)
2018
Achievement of the first plasma
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Whats ITER ?

Nuclear fusion
Very high energy
Heating of cooling water
Vapor generator
Turbo generator
Power generation
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Whats ITER ?
Vacuum vessel
TF coil
Interception of neutron
Taking out of heat
Future
Heating
Heating
Plasma
Neutron
Lithium
Reaction
Fuel
Fuel
Blanket
Tritium
PF coil
Diverter
CS coil
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Whats ITER ?
Vacuum vessel
TF coil
Plasma space
Heating
Heating
Plasma
Neutron
Vacuum
Fuel
Fuel
Blanket
PF coil
Diverter
CS coil
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Whats ITER ?
Vacuum vessel
TF coil
Removal of extra energy
Heating
Heating
Plasma
Neutron
Removal of helium gas and impurities
Fuel
Fuel
Blanket
CS coil
PF coil
Diverter
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Whats ITER ?
It confined plasma in the powerful magnetic field.
Vacuum vessel
TF coil
Reaction
Heating
Heating
Tritium
Plasma
Neutron
Fuel
Fuel
Blanket
PF coil
Diverter
CS coil
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Whats ITER ?
Vacuum vessel
TF coil
It generates the current in plasma.
Heating
Heating
Plasma
Neutron
Ignition of plasma
Fuel
Fuel
Blanket
PF coil
CS coil
Diverter
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Whats ITER ?
Vacuum vessel
TF coil
A part of the magnetic field to confine plasma
is supplied.
Heating
Heating
Plasma
Neutron
It controls the position and the shape of plasma.
Fuel
Fuel
Blanket
PF coil
Diverter
CS coil
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Comparison of coils
Cu coil
Superconductive coil
Increase of resistance by generation of heat
A large current can be thrown for a long time.
It energizes in a short time.
The electrical resistance loss of the coil is
almost 0.
Energy into which the electrical resistance loss
of the coil generated electricity is greatly
exceeded.
The majority of the fusion energy can be used as
electricity.
Necessary
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Problem and current state of superconducting coil
Problem
Powerful electromagnetic force
Quench
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Detailed design of the ITER central solenoid
P.Libeyre , N.Mitchell , D.Bessette , Y.Gribov ,
C.Jong , C.Lyraud
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Introduction
CS coil achieves 3 functions .
Production of the inductive flux to drive the
plasma
Shaping of the field lines in the divertor region
Control of the vertical stability
The present design
It satisfies the requirement of ITER
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Introduction
Table 1 ITER CS main parameters.
Fig. 1. The ITER central solenoid.
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Plasma operation
all CS modules initially magnetized are
discharged on resistors of the switching network
units (SNU) inducing the toroidal electrical
field inside the vacuum vessel
breakdown of the gas
its ionization and generates plasma current.
a maximum voltage of 10 kV
a maximum field on the conductor of 13 T
The maximum current in the central modules
is reached at the end of burn, but with a maximum
magnetic field of 12.4 T.
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Coil design
Nb3Sn model coil
Very sensitive to strain
Nb3Sn
As a structural material the conductor jacket has
to resist the large electromagnetic forces
arising during operation and to demonstrate a
good fatigue behaviour.
(JK2LB stainless steal)
JK2LB stainless steal
Fig. 2. The CS conductor.
It was selected in order to withstand the planned
60,000 cycles (2 cycles per burn) during
operation.
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Coil design
The winding pack of one module is a stack of 6
hexa pancakes with one quad pancake in the
middle.
1.5 nO
outbursting hoop force
locked to the last-but- one turn to withstand
Fig. 3. CS module.
It is giving a high voltage operating capability
(test voltage 29kV)
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Coil design
Electrical supply
Each CS module is energised independently with
its own power supply
Cooling
Fig. 4. Connection of the CS modules to the
feeders.
All modules are cooled in parallel.
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Precompression structure
The precompression structure is needed to avoid
separation of the modules during operation
Allow radial breathing of the stack assembly.
An additional precompression is provided during
cooldown by the differential thermal contraction
between the stainless steel tie-plates and the
JK2LB buffer zones.
The mechanical analysis of the CS during
operation
Fig. 5. Precompression structure.
An average axial precompression of 26MPa applied
on the whole surface of the modules after
cooldown prevents any vertical gap between
modules from occurring.
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Conclusions
The detailed design of the central solenoid which
has been developed combines modularity and tight
arrangement in a restricted narrow space to allow
maximum flexibility during plasma operation.
Production of detailed drawings is underway
installation of helium distribution inside
A modular precompression structure achieve axial
precompression
Production of detailed drawings is underway.
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References
(1)???? ???????????? (2006) (2)?????
???????????? ??????? ?3? (2009) (3)??????????????
??? ????????????? ???????? ?994? (2005) (3) ???,
????, ????, ???, ????, ??? ??????????ITER????????
?? ????????? ASC-09-8 (2009) (4) P.Libeyre ,
N.Mitchell , D.Bessette , Y.Gribov , C.Jong ,
C.Lyraud ? Detailed design of the ITER central
solenoid ?, (2009)