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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 :
Give sustained power for the future
As on Dec. 2008, total installed capacity is 147 GW
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 re-processed to produce fuel for the next stage)
• First stage – Pressurized Heavy Water Reactors (PHWR) [U235+U238 small quantity of Pu239 produced and re-processed 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
R. B. Grover et al., Energy Policy (2006) 2834
• 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
# Shah RKD, Indian National Academy of Engineering (1998)
Installed capacity : Beyond 2050
Without fusion With 10 % fusion
Shows 890 GWe (34 %) by Nuclear in 2100
Fall of contribution from coal near 2100. 2 GWe by 2060 and 250 GWe (10%) by fusion in 2100R. Srinivasan and the Indian
DEMO Team, JPFRS (2010)
Indian Fusion Program
ADITYA Tokamak
1986Steady State Physics and
related technologies
SST-1 2004
scientific and technological feasibility of fusion energy
ITER Participation 2005
• Qualification of Technologies• Qualification of reactor
components & Process• Qualification of materials
DEMO 2037
Fusion Test Reactor (FTR)
2022
Fusion Power Reactor
Power Plant 2050
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 A, HH, n/nGW
Ipq95, Btmax,BS,,
R0, a, Bt,n,nGW
Q Pfus
Paux
EPower balance
T
Check for Pfus, Q
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
Model : ITER-FEAT
Fusion Test Reactor (FTR) Parameters
FW : First WallTFC : Toroidal Field Coil SOL : Scrape of LayerVV : Vacuum VesselCS : Central SolenoidTF : Toroidal Field
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)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 0.93Plasma 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
Coupling of energy and fuel between fusion and fission reactors
Fission Reactor (Th-U233 Cycle)
Fusion Test Reactor
(FTR)
Lithium Thorium
Thorium To Grid
Deuterium
U233 Tritium
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
Inboard
Structural material: RAFMSFission breeder: ThoriumVacuum 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.
The neutronics model describes the blankets, vacuum vessel and TF coils.
Outboard
FTR 1-d radial view
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.
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.
Plasma
1-d FTR top view
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