Transcript R. Srinivasan

Indian Fusion Test Reactor
R. Srinivasan and the FTR Team
Institute for Plasma Research,
Bhat, Gandhinagar – 382 428, India.
Energy scenario in India
Fission reactors to supply
the immediate needs
Projection – 30GWe by
2020 (7 % of total) and 20
% by 2050
Fusion reactors :
As on Dec. 2008, total installed
capacity is 147 GW
Give sustained power for
the future
Available energy resources
• Fossil (coal & Hydrocarbon)
7614 GWeYr
• Renewable (Hydro & Non. Conv.) 102 GWeYr
• Nuclear
– Uranium (PHWR & FBR)
42,559 GWeYr
– Thorium
155,502 GWeYr
To achieve 550 ppm level in the period 1990-2100,
one may expect the emission from India should not
exceed 7.5 % of the global emissions (980 GtC)# .
# T. Hamacher, R. P. Shukla, A. J. Seebregts, FED 69 (2003) 733.
Three-stage nuclear program
• Utilization of indigenous nuclear resources (modest
Uranium and abundant Thorium)
• Based on closed fuel cycle (spent fuel of one stage reprocessed to produce fuel for the next stage)
• First stage – Pressurized Heavy Water Reactors (PHWR)
[U235+U238 small quantity of Pu239 produced and reprocessed for the next stage]
• Second stage – Fast Breeder Reactor (FBR)[U238+Pu239
 Pu239+energy]
– Over a period of time Pu inventory can be built
– Thorium will be used as blanket material to produce U233
• Third stage is with U233 and lead to very large production
of electricity
• Accelerator Driven System (ADS)  direct usage of
Thorium (in addition to 3-stage program)
Population Growth
• Data from R. B. Grover
et al. Energy Policy
(2006) 2834.
• 1991 0.843 B
• 2001 1.027 B
• Rest is projected
• Population will
stabilize by 2050
Installed capacity
• 1947  1363 MWe
• 1980-81  30,214 MWe
• 1990-91  66,086 MWe#
• 2003
 138,730 MWe
• Growth rates : 9.54,8.14
and 6.26%/yr
• Beyond 2022, intensity fall
by 1.2 %/yr
R. B. Grover et al., Energy Policy (2006) 2834
#
Shah RKD, Indian National
Academy of Engineering (1998)
Installed capacity : Beyond 2050
Without fusion
Shows 890 GWe (34 %) by Nuclear
in 2100
R. Srinivasan and the Indian
DEMO Team, JPFRS (2010)
With 10 % fusion
Fall of contribution from coal near
2100. 2 GWe by 2060 and 250 GWe
(10%) by fusion in 2100
Indian Fusion Program
Power Plant 2050
Fusion Power Reactor
2037
DEMO
• Qualification of Technologies
• Qualification of reactor
components & Process
• Qualification of materials
2022
Fusion Test Reactor (FTR)
ITER Participation 2005
scientific and technological
feasibility of fusion energy
SST-1 2004
1986
ADITYA Tokamak
Steady State Physics and
related technologies
2 x 1GWe Power
plant by 2060
Fusion Test Reactor
• Fission suppressed hybrid reactor to produce fissile fuel
• Medium size tokamak device with Q ~ 3 -5
• Capable of producing about 50 Kg fissile U-233 in one
FPY (try to attain fuel for 250 MW fission reactor)
• Build with available technologies and materials
• Neutron wall load should be up to 0.25 MW/m2 (existing
technologies can be used)
• Should have tritium breeding blankets to produce the
tritium required for self-sufficiency (try to achieve)
• Auxiliary power should be around 20 MW (realizable with
present capabilities)
FTR : Physics design
• Fusion performance or fusion gain (Q) has to be around
3-5
• Further gain will be achieved from burning fissile fuel
(Qhyb ~ [7-10] Qfus)
• Fusion power and availability (20 – 50 %) decides the
amount of fissile breeding
• Q depends on plasma performance
–
–
–
–
–
Confinement time
Impurity level
n/nGW
N
Normalized power crossing the separatrix
• In-directly depends on the geometry of the system
– Maximum toroidal field at the TF conductor
– Area available for the neutron load (breeding and damage)
– Area available for the heat removal
(IpHHA[n/nGW ])3=f(Q)G
Ip
A, HH, n/nGW
Q
q95, Btmax,BS,,
Paux
R0, a, Bt,n,nGW
Check for
Pfus, Q
Pfus
Power balance
E
T
Model : ITER-FEAT
Plasma
parameters
ITER-FEAT
Model prediction
R0
6.2
6.13
a
2.0
1.98
Bt (T)
5.3
5.4
Ip(MA)
15.0
15.1
Ploss/PLH
2.5
2.1
Pfusion (MW)
500
500
Paux(MW)
50
50
<n20>
1.1
1.1
<T> keV
8.9
8.9
N
2.0
1.9
Fusion Test Reactor (FTR) Parameters
Plasma Parameters for FTR
Plasma Parameters
Major Radius R0 (m)
4.4
Minor Radius a (m)
1.5
Aspect Ratio (A)
3.0
Toroidal Magnetic field Bt
(T)
FW : First Wall
TFC : Toroidal Field Coil
SOL : Scrape of Layer
VV : Vacuum Vessel
CS : Central Solenoid
TF : Toroidal Field
5.4
N
1.3
Plasma Current Ip(MA)
11.2
fbs(%)
12
Power Loss, Ploss(MW)
40
Fusion Power Pfusion (MW)
100
Auxiliary heating Paux(MW)
20
Power gain Q
5
n/nGW
0.93
Plasma Temperature
<T>keV
4.5
Hybrid reactor fuel cycle
• Thorium is a naturally occurring, mildly radioactive element
• Thorium as a nuclear fuel has been proposed for various nuclear reactors.
• Tritium bred in the reactor has to be used as fuel
Thorium
To Grid
Lithium
Fission Reactor (ThU233 Cycle)
Deuterium
Thorium
Fusion Test Reactor
(FTR)
U233
Tritium
Coupling of energy and fuel between fusion and fission reactors
1-D nuclear design and
analysis of FTR
FTR: Radial build-up
The tritium breeding blanket concept is Lead Lithium cooled Ceramic Breeder (LLCB)
LLCB concept
1-D nuclear model: Radial view
Structural material: RAFMS
Fission breeder: Thorium
Vacuum Vessel and shield: SS316+water
 Monte Carlo tool and Fendl-2.1 has
been used.
1-D nuclear model has been prepared
using concentric cylinders.
Reflecting boundary conditions are applied
at the top and bottom of the cylinders.
 A 14 MeV D-T neutron source has also
been modeled using cylinders.
Inboard
FTR 1-d radial view
Outboard
The neutronics model describes the
blankets, vacuum vessel and TF coils.
1-d nuclear model: Top view
In the present blanket design, we
considered Pb-Li eutectic as tritium
breeder at the inboard side. At the
outboard side the neutrons first enter
into the fission blanket and then they
pass through the tritium breeding
blanket.
Plasma
1-d FTR top view
Nuclear responses such as neutron
fluxes, Uranium-233 production in
fission blanket, tritium production in
fusion breeder blanket and radiation
damage in steel structure have been
calculated.
Main results
• The total amount of U-232 produced in fission
blanket (by the neutron capture in Th-232) is ~
1.975 mg/s. In a Full Power Year operation of FTR
it is expected to produce ~ 62.3 kg of U-233.
• The total tritium atoms produced is 3.9112E+19
per second and in the present blanket
configuration, TBR value is found to be 1.1
• It is expected that the five FPY operation of FTR
will cause around 8 dpa at outboard mid-plane first
wall location.
Conclusions
• Fusion has an important role in reducing CO2 emission
• An accelerated fusion program with fission can meet this
requirement
• Hybrid reactors can support the fission reactor program
in a major way
• Medium size device can produce about 50 kg/FPY
• Fissile fuel for fission reactors with 250 MW power can
be supplied with FTR like device
• The projected nuclear power growth (20 %) by 2050 can
be achieved early through fission suppressed hybrid
program
Thank you