Indian nuclear power programme
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Transcript of Indian nuclear power programme
NUCLEAR POWER SCENARIO IN INDIA : REALITY
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Indian Nuclear Power
Programme
It’s Three stage nuclear power programme.
Stage 1 - PHWR(Pressure Heavy Water Reactor)
Stage 2 - FBTR (Fast Breeder Test Reactor)Stage 3 - AHWR thorium
(Advanced Heavy Water Reactor)
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Stage – I PHWRs
• 14 - Operating
• 4 - Under construction
• Several others planned
• Scaling to 700 MWe
• Gestation period has
been reduced• POWER POTENTIAL
10,000 MWe
LWRs
• 2 BWRs Operating
• 2 VVERs under
construction
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Avail
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Three Stage Nuclear Power Programme
Stage - II
Fast Breeder Reactors
• 40 MWth FBTR -
Operating since 1985
Technology Objectives
realised
• 500 MWe PFBR-
Under Construction
• POWER POTENTIAL
530,000 MWe
Stage - III
Thorium Based Reactors
• 30 kWth KAMINI- Operating
• 300 MWe AHWR-
Under Development
POWER POTENTIAL IS
VERY LARGE
Availability of ADS can enable
early introduction of
Thorium on a large
scale
World class
performance
Globally Advanced
TechnologyGlobally Unique
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India’s Nuclear Resource Base
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Aim of programme
A closed fuel cycle approach involving
reprocessing of spent fuel to separate the useful
fissile and fertile isotopes from spent fuel and
reusing them in nuclear reactors has been adopted
as a guiding principle for our nuclear energy
programme to ensure long term energy security for
the country
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India’s Nuclear Power Programme
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NUCLEAR POWERINDIAN stand
Clean source of energy along with otherrenewable sources
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ADVANTAGES
ECO FRIENDLY
ENORMOUS ENERGY
AVAILABLE TECHNOLOGY
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FISSION- NEUTRONS rule the
nuclear reactor
The opposite of fission is fusion. Sun is a natural fusion reactor constantly producing energy that sustains life on earth. 11
NUCLEAR POWER : A DANGEROUS
TECHNOLOGY
HAZARDS OF RADIOACTIVITY
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REACTOR SAFETY
HEADACHE OF NUCLEAR WASTE
NOT SUSTAINABLE
POTENTIAL TERRORISTS TARGET
“ The more nuclear power plants, higher is the probability of nuclear disaster ”
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Nuclear accidents & protests in INDIA November 2009 Fifty-five employees consume
radioactive material after tritiated water finds its way into the drinking water cooler in Kaiga Generating Station.
January 2003 Failure of a valve in the Kalpakkam Atomic Reprocessing Plant in Tamil Nadu results in the release of high-level waste, exposing six workers to high doses of radiation. The leaking area of the plant had no radiation monitors or mechanisms to detect valve failure.
December 1991 A leak from pipelines at the Bhabha Atomic Research Centre (BARC) in Maharashtra, results in severe Cs-137 soil contamination. Local vegetation was also found to be contaminated. 14
“ If Japan isn’t capable of protecting its nuclear power plants from earthquakes/tsunamis, is India smarter ? ”
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FBR Design
1) Highly enriched uranium
or plutonium
2) Control rods (same
material as core)
3) Depleted uranium
4) Heat is transferred from
primary to secondary
sodium
5) Heat is transferred from
secondary sodium to
water
Figure: Baksiden, modified by Martin Metzner17
Nuclear Fuel
Initially FBRs were designed to use pure uranium oxide fuel
Eventually switched to MOX◦ Mixed oxide fuel (MOX):
Mixture of UO2 and PuO2
Already an existing source of fissile plutonium◦ Nuclear warheads
Highly enriched, former USSR and USA currently dismantling arsenals
◦ Depleted PWR fuel Low enrichment caused by the fusion of U-238 and a
neutron
Must be processed before it can be used
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Fast Breeder Reactors vs. Pressurized Water
Reactors
FBR
◦ Fuel is enriched to
15-20%
◦ Moderator: none
◦ Heat transfer by
liquid metal or metal
alloys
Typically sodium
◦ Reactor under low
pressure
◦ ~1.2 fissile atoms
produced per fission
PWR
◦ Fuel is enriched to
3-5%
◦ Moderator: water
◦ Heat transfer by
water
◦ Reactor under high
pressure
◦ Fissile material is
only consumed
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ADVANCED HEAVY WATER REACTOR
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911
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1214
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3
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1
2 Primary Containment
1 Secondary Containment
3 Gravity Driven Water Pool
4 Isolation Condenser
5 Passive Containment Isolation Duct
6 Vent Pipe
7 Tail Pipe Tower
8 Steam Drum
9 100 M Floor
10 Fuelling Machine
11 Deck Plate
13 Header
14 Pile Supports
15 Advanced Accumulator
17 Passive Containment Cooler
16 Pre - Stressing Gallery
12 Calandria with End Shield
• Structured peer
review
completed
• Pre-licensing
design safety
appraisal by
AERB in
progress
• BASIC DATA
FUEL : U-233/THORIUM MOX
+ Pu-239/THORIUM MOX
COOLANT : BOILING LIGHT
WATER
MODERATOR : HEAVY WATER
POWER : 300 MW(e)
920 MW(t)
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Written
Editing
Formatting
by
Madhumitha (EE12B1005)
Mohamed Sha(EE12B1006)
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