Nuclear power plant

CONTENTS
 Introduction
 Nuclear fuel
 Nuclear fission process
 Nuclear chain reaction
 Constituents of Nuclear power plant
 Types of power reactors commonly used
 Advantages and Disadvantages
 World’s Nuclear power program
 India’s Nuclear power program
 Design features of Reactor containment
Presented By : Omraj Singh

NUCLEAR FUEL
Nuclear fuel is any material that can be consumed to derive nuclear energy.
The most common type of nuclear fuel is fissile elements that can be made to
undergo nuclear fission chain reactions in a nuclear reactor.
The most common nuclear fuels are 235U and 239Pu. Not all nuclear fuels
are used in fission chain reactions.
NUCLEAR FISSION
When a neutron strikes an atom of Uranium, the Uranium splits into two
lighter atoms and releases heat simultaneously.
Fission of heavy elements is an exothermic reaction which can release large
amounts of energy both as electromagnetic radiation and as kinetic energy of
the fragments.

NUCLEAR CHAIN REACTIONS
A chain reaction refers to a process in which neutrons released in fission
produce an additional fission in at least one further nucleus. This nucleus in
turn produces neutrons, and the process repeats. If the process is controlled
it is used for nuclear power or if uncontrolled it is used for nuclear weapons.
U235 + n fission + → 2 or 3 n + 200 MeV
If each neutron releases two more neutrons, then the number of fissions
doubles each generation. In that case, in 10 generations there are 1,024
fissions and in 80 generations about 6 x 10 23 (a mole) fissions.

NUCLEAR CHAIN
Presented By : Omraj Singh REACTION

NUCLEAR REACTOR
A nuclear reactor is a device in which nuclear chain reactions are
initiated, controlled, and sustained at a steady rate, as opposed to a
nuclear bomb, in which the chain reaction occurs in a fraction of a
second and is uncontrolled causing an explosion.

NUCLEAR POWER PLANT

MAIN COMPONENTS OF NUCLEAR POWER
PLANT
 Fuel Rods -
• Tube filled with pellets of Uranium
 Shielding -
• Protection against alpha, beta and Gamma Rays
 Moderator -
• Slow down the neutron release(Heavy water, Beryllium,
Graphite)
 Control Rods -
• Control rods made of a material material (boron Carbide,
cadmium) that absorbs neutrons are inserted into the bundle
using a mechanism that can rise or lower the control rods.
• The control rods essentially contain neutron absorbers like,
boron, cadmium or indium. Presented By : Omraj Singh

PLANT
 Coolant -
• To transfer the heat generated inside the reactor to a heat
exchanger for utilization of power generation
• Either ordinary water or heavy water is used as the coolant
 Containment -
• Concrete lined cavity acting as a radiation shield
 Steam Generator s-
• Steam generators are heat exchangers used to convert water
into steam from heat produced in a nuclear reactor core
 Steam Separator -
• Steam from the heated coolant is fed to the turbines to produce
electricity from generator

PLANT
 Steam Turbine -
• A steam turbine is a mechanical device that extracts thermal
energy from pressurized steam, and converts it into useful
mechanical
• Various high-performance alloys and super alloys have been
used for steam generator tubing
 Coolant Pump -
• The coolant pump pressurizes the coolant to pressures of the
order of 155bar
• The pressure of the coolant loop is maintained almost constant
with the help of the pump and a pressurizer unit.

PLANT
 Feed Pump -
• Steam coming out of the turbine, flows through the condenser
for condensation and re-circulated for the next cycle of
operation
• The feed pump circulates the condensed water in the working
fluid loop.
 Condenser-
• Condenser is a device or unit which is used to condense
vapor into liquid
• The objective of the condenser are to reduce the turbine
exhaust pressure to increase the efficiency and to recover high
quality feed water in the form of condensate & feed back it to
the steam generator without any further treatment.

PLANT
 Cooling Towers-
• Cooling towers are heat removal devices used to transfer
process waste heat to the atmosphere
• Water circulating through the condenser is taken to the cooling
tower for cooling and reuse

TYPES OF POWER REACTORS COMMONLY
USED
 Boiling water Reactor(BWR)
 Pressurized water Reactor(PWR)
 Pressurized Heavy Water Reactors(PHWR) OR CANDU Type
Reactor
 Gas Cooled Reactor
 Liquid Metal Cooled Reactor

BOILING WATER REACTOR (BWR)
 Heat generated in the core is used to generated steam through a
heat exchanger
 The steam runs a turbine just like a normal power plant
 Fuel used is rich in uranium oxide
 Ordinary water is used as both moderator and coolant
 Low thermal efficiency
 Can’t meet sudden increase
of load

PRESSURIZED WATER REACTOR
(PWR)
 Water in the core heated top 315°C but is not turned into steam due
to high pressure in the primary loop
 Heat exchanger used to transfer heat into secondary loop where
water is turned to steam to power turbine power plant
 Steam used to power turbine never comes directly in contact
with radioactive materials
 Strong pressure vessel is
required
 High loss from heat exchanger

PRESSURIZED HEAVY WATER
REACTOR
(PHWR) OR CANDU TYPE
REACTOR
 It makes use of heavy hydrogen (deuterium oxide D2 O) as moderator
 Primary and secondary circuits are similar to PWR
 It’s very expensive to separate
 Control rods are not required
 It has high multiplication factor and low level fuel consumption

ADVANTAGES
 Nuclear power generation does emit relatively low amounts of carbon dioxide
(CO2). The emissions of green house gases and therefore the contribution of
nuclear power plants to global warming is therefore relatively little.
 This technology is readily available, it does not have to be developed first.
 It is possible to generate a high amount of electrical energy in one single plant.
Highly Concentrated Source of Energy
1 kg wood: 1 kW·h
1 kg coal: 3 kW·h
1 kg oil: 4 kW·h
1 kg uranium: 50 000 kW·h
(3 500 000 kW·h with reprocessing)
 Nuclear Power: a Compact Source
Typical Fossil & Nuclear Sites : 1–4 km²
Solar thermal or photovoltaic (PV ) parks : 20–50 km²
Wind fields : 50–150 km²
Biomass plantations : 4000–6000 km² (a province)

DISADVANTAGES
 The problem of radioactive waste is still an unsolved one.
 High risks: It is technically impossible to build a plant with 100% security.
 The energy source for nuclear energy is Uranium. Uranium is a scarce
resource, its supply is estimated to last only for the next 30 to 60 years
depending on the actual demand.
 Nuclear power plants as well as nuclear waste cloud be preferred targets for
terrorist attacks.
 During the operation of nuclear power plants, radioactive waste is
production, which in turn can be used for production of nuclear weapons.

WORLD’S NUCLEAR POWER
PROGRAM

Source: International Energy Outlook 2010

NUCLEAR POWER PLANT STATUS IN TH E
WORLD
Present Status (As of Aug 2011)
* No of Units in Operation:432
* Total Installed Capacity: 365837 (MWe)
* No of Units under Construction: 62
* Total Installed Capacity: 62862 (MWe) (Source: IAEA)

(Source: IAEA) Presented By : Omraj Singh

INDIA’S NUCLEAR POWER
PROGRAM

INIDA’S NUCLEAR POWER PROGRAM
India now envisages to increase the contribution of nuclear power to overall
electricity generation capacity from 4.2% to 9% within 25 years. In 2010,
India's installed nuclear power generation capacity will increase to
6,000 MW. Indian nuclear power industry is expected to undergo a
significant expansion in the coming years in part to the passing of the U.S.-
India Civil Nuclear Agreement . This agreement will allow India to carry out
trade of nuclear fuel and technologies with other countries and significantly
enhance its power generation capacity. When the agreement goes through,
India is expected to generate an additional 25,000 MW of nuclear power by
2020, bringing total estimated nuclear power generation to 45,000 MW.

Three Stage Nuclear Power Program
Closed Fuel Cycle
First Stage has reached a level of maturity
540 MW and 700 MW reactors of Indigenous design
Second Stage: 500 MW PFBR under construction
3rd Stage AHWR : Construction expected to start in next 1 to 2 years

INDIA’s
THREE STAGE
NUCLEAR
POWER
PROGRAMME

PROPOSED XI PLAN STARTS PROJECTS – NPCIL MAJOR
Indigenous
Project Construction
Start
1. KAPP 3&4 (2X700 MWe PHWRs) 2008-09
2. RAPP 7&8 (2X700 MWe PHWRs) 2009-10
3. 7NP 5&6 (2X700 MWe PHWRs) 2011-12
4. 7NP 7&8 (2X700 MWe PHWRs) Pre- Project
Imports
Project Construction
Start
1. KK 3&4 2007-08
2. JAITAPUR 1&2 2008-09
3. KK 5&6 2010-11
4. LWR 11&12 2010-11
5. JAITAPUR 3&4 2011-12

3360
NUCLEAR POWER CAPACITY
BUILD-UP
(WITH XI PLAN PROPOSALS)
With international co-operation
Indigenous and ongoing LWRs
4120
4780
5780
6780
7280
7280
7280
9280
12680
14380
19780
23180
3360
4120
4780
5780
6780
7280
7280
7280
7280
8680
10380
11780
13180
25000
20000
15000
10000
5000
0
05-06 06-07 07-08 08-09 09-10 10-11 11-12 12-13 13-14 14-15 15-16 16-17 17-18

INDIA’S OPERATING NUCLEAR POWER REACTORS
Reactor State Type MWe net,
each
Commercial
operation
Safeguards
status
Tarapur 1 & 2 Maharashtra BWR 150 1969 item-specific
Kaiga 1 & 2 Karnataka PHWR 202 1999-2000
Kaiga 3 & 4 Karnataka PHWR 202 2007, (due 2011)
Kakrapar 1 & 2 Gujarat PHWR 202 1993-95
December 2010
under new
agreement
Madras 1 & 2
(MAPS) Tamil Nadu PHWR 202 1984-86
Narora 1 & 2 Uttar Pradesh PHWR 202 1991-92 in 2014 under new
agreement
Rajasthan 1 Rajasthan PHWR 90 1973 item-specific
Rajasthan 2 Rajasthan PHWR 187 1981 item-specific
Rajasthan 3 & 4 Rajasthan PHWR 202 1999-2000 early 2010 under
new agreement
Rajasthan 5 & 6 Rajasthan PHWR 202 Feb & April 2010 Oct 2009 under
new agreement
Tarapur 3 & 4 Maharashtra PHWR 490 2006, 05
Total (20) 4385 MWe

INDIA’S NUCLEAR POWER REACTORS UNDER CONSTRUCTION
Reactor Type
MWe gross,
net,
each
Projec
t
contro
l
Constructi
on start
Commercia
l
operation
due
Safeguard
s status
Kudankulam 1 PWR (VVER) 1000, 950 NPCIL March 2002
October 2011?
item-specific
Kudankulam 2 PWR (VVER) 1000, 950 NPCIL July 2002 June 2012 item-specific
Kalpakkam PFBR FBR 500, 470 Bhavini Oct 2004 9/2011, or
2012 -
Kakrapar 3 PHWR 700, 630 NPCIL Nov 2010 June 2015
Kakrapar 4 PHWR 700, 630 NPCIL March 2011 Dec 2015
Rajasthan 7 PHWR 700, 630 NPCIL July 2011 Dec 2016
Total (6) 4260 MWe net,
4600 MWe gross

DESIGN FEATURES OF REACTOR
CONTAINMENT

EFFECT OF SITE CHARACTERISTICS ON NUCLEAR
POWER PLANT
1. Natural Events
(a) Seismic Consideration
 Site should not lie in seismic zone V as per IS 1893 ( Part area of J&K ,
Uttaranchal , North east , Kutch etc.) – rejection criteria
 No Capable fault within 5 Km - Seism tectonic evaluation needed –
rejection criteria
 All lineaments within 300 km radius are studied
 Evaluation for Liquefaction – rejection criteria
 Effect of Tsunami

POWER PLANT
( b) Geological Considerations
 Competent strata exist
 Adequate sub soil investigation ( 6 boreholes during sitting)
 Seismic logging of foundation strata
 Evaluate for slope instability ( such as land slide , land erosion)
 Evaluate for existence of mines , oil wells , subsidence

POWER PLANT
(c) Flooding of Site
 All historical rainfall , flood data examined
 Flooding due to precipitation
 Flooding due to up stream dam break
 Finished grade level higher than both these floods
 Coastal sites evaluated for combination of high tides , wind effects, wave run
up
 Studies done at detailed Site Evaluation stage
• – 1000 year return period daily rainfall evaluated from Annual maximum
daily rainfall series
• 1000 year return period flood evaluated from annual maximum flood
series
• Design Basis Flood calculated from worst combination of events

POWER PLANT
(d) Extreme Meteorological Events
 Two level of wind effects are considered
• - Severe wind 1000 year return period for design purpose
• - Extreme wind 10000 year return period for wind induced missiles
 Wind speed and wind rose
 Extreme temperatures
(e) Loss of ultimate heat sink – Failure of down stream dam – 7
days storage is provided

EFFECT OF SITE CHARACTERISTICS ON
NUCLEAR POWER PLANT
2. Man- Induced Events
Aircraft Crash- Screening Distance Values (SDV) are used
Distance from small airfields More than 5 km.
Distance from major airports More than 8 km.
Distance from military airfields More than 15 km.

THANK YOU

Nuclear power plant

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