10-09-2013, 12:11 PM
Indian Fusion Test Reactor
Fusion Test Reactor.ppt (Size: 1.01 MB / Downloads: 80)
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)
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
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