Indian Fusion Test Reactor R. Srinivasan and the FTR Team Institute for Plasma Research, Bhat, Gandhinagar – 382 428, India.

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