The document summarizes a presentation on the Tarapur nuclear power plant in India. It provides background that Tarapur was India's first nuclear power plant, constructed in 1963 under an agreement with the US. It then covers key topics about nuclear energy and power plants including: nuclear fission and chain reactions, components of nuclear reactors like the core and control rods, the two main types of reactors (BWR and PHWR) used at Tarapur, nuclear waste disposal methods, advantages and disadvantages of nuclear power, and the future potential of nuclear energy in India.

1. SYNERGY INSTITUTE OF ENGINEERING AND TECHNOLOGY, DHENKANAL
PRESENTATION ON:- Tarapur nuclear power plant- A case study
Presentation by:-JEEBAN JYOTI MOHANTY
REG.NO:-1601230151
ROLL.NO:-EE-16-19
Guided by:- Mr P.K.NAYAK
DEPARTMENT OF ELECTRICAL ENGINEERING

2. CONTENTS
 Introduction
 Nuclear energy
 Nuclear fission and chain reaction
 Nuclear power plant
 Nuclear reactor
 Components of nuclear reactor
 Types of nuclear reactor
 Nuclear waste
 Advantages and disadvantages
 Future scope
 Conclusion
 Reference

3. INTRODUCTION
 Tarapur Atomic power station was 1st Nuclear power plant in India.
 It was constructed with an agreement between India and U.S.A. in
1963 and plant get operation on 1969 with a two BWR units of
160Mwe.
 In 2005 & 2006 two new PHWR units are developed of 540Mwe.
 Today Tarapur Atomic power plant producing 1400Mw power is
generated, capacity factor of 39.4% and annual net output is
4829GW-h.

4. What is Nuclear Energy?
 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.
 Otherfuels:238Np(Neptunium),239U(Uranium),241Pu(plutoni
um).

5. 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.

7. Chain Reaction
 A chain reaction is that process in which number of neutrons keep on
multiplying rapidly during fission till whole of the fissionable material is
disintegrated.
 Chain reaction will continue if, for every neutron absorbed, at least one fission
neutron becomes available for causing fission of another nucleus.
 Expressed by multiplication factor
 K= No. of neutrons in any particular generation/No. of neutrons in the
preceding generation.
 If K>1, chain reaction will continue and if K<1 , cant be maintained.

9. Schemetric diagram of Nuclear power plant

10. Nuclear reactor
A Nuclear reactor is an
apparatus in which nuclear
fission is produced in the
form of a controlled self
sustaining chain reaction.

11. Components of nuclear reactor
1. Reactor core
2. Reflector
3. Control mechanism
4. Moderator
5. Coolants
6. Measuring instruments
7. Shielding

12.  Reactor Core :This is the main part of reactor which contain the
fissionable material called reactor fuel. Fission energy is liberated
in the form of heat for operating power conversion equipment. The
fuel element are made of plate of rods of uranium.
 Reactor reflector :The region surrounding the reactor core is
known as reflector. Its function is to reflect back some of the
neutron that leak out from the surface of core.
 Control rods :The rate of reaction in a nuclear reactor is
controlled by control rods. Since the neutron are responsible for the
progress of chain reaction, suitable neutron absorber are required to
control the rate of reaction.

13.  Moderator :The function of a reactor is to slow down the fast
neutron.
 The moderator should have
 High slowing down power
 Non corrosiveness
 High melting point for solids and low melting point for liquids.
 Chemical and radiation stability.
 High thermal conductivity
 Abundance in pure form.
 The commonly used moderator are :
(I) Ordinary water (II) Heavy water (III) Graphite.

14.  Coolant :The material used to remove heat produce by fission as fast as
liberated is known as reactor coolant. The coolant generally pumped through
the reactor in the form of liquid or gas. It is circulated throughout the reactor
so as to maintain a uniform temperature.
 Measuring Instruments: Main instrument required is for the purpose of
measuring thermal neutron flux which determines the power developed by
the reactor.
 Shielding: The large steel recipient containing the core, the control rods and
the heat-transfer fluid.
 All the components of the reactor are container in a solid concrete structure
that guarantees further isolation from external environment. This structure is
made of concrete that is one-metre thick, covered by steel.

15. TYPES OF NUCLEAR REACTOR
Reactor Type Boiling Water Reactor
(BWR)
Pressurised Heavy Water
Reactor (PHWR)
Purpose electricity electricity; plutonium production
Coolant Type water (H2O) heavy water (deuterium oxide,
D2O)
Moderator Type water heavy water
Fuel — Chemical
Composition
uranium-dioxide (UO2) uranium-dioxide or metal
Fuel – Enrichment Level low-enriched natural uranium (not enriched)

16. Boiling water reactors (BWS)

17. Pressurized heavy water reactor (PHWR)

18. Nuclear waste disposal
 Geological Disposal
 Reprocessing
 Transmutation

19. Geological Disposal
The process of geological disposal
centers on burrowing nuclear waste
into the ground to the point where it is
out of human reach.
• The waste needs to be properly
protected to stop any material from
leaking out. Seepage from the waste
could contaminate the water table if the
burial location is above or below the
water level. Furthermore, the waste
needs to be properly fastened to the
burial site and also structurally
supported in the event of a major
seismic event, which could result in
immediate contamination.

20. Reprocessing
Reprocessing has also emerged as
a viable long term method for
dealing with waste.
As the name implies, the process
involves taking waste and
separating the useful components
from those that aren’t as useful.
Specifically, it involves taking the
fissionable material out from the
irradiated nuclear fuel.

21. Transmutation
 Transmutation is a process in
which the long-lived radioactive
elements in waste are converted
by fission to shorter-lived
particles that produce radiation
for a much shorter period and
are less radiotoxic.
 Transmutation can therefore
greatly reduce the amount and
radiotoxicity of high-level
radioactive waste.

22. Advantages and Disadvantages
Advantages Disadvantages
Produces no polluting gases Waste is radioactive and safe disposal is very
difficult and expensive.
Does not contribute to global warming Local thermal pollution from wastewater affects
marine life
Very low fuel costs Large-scale accidents can be catastrophic
Low fuel quantity reduces mining and
transportation effects on environment
Public perception of nuclear power is negative
High technology research required benefits other
industries
Costs of building and safely decommissioning are
very high
Power station has very long lifetime Cannot react quickly to changes in electricity
demand

23. Future scope
India has adequate deposits of fissionable material Thorium which
can be eventually used for generation of power. The future of
nuclear power plant is quiet bright
• Following three factors need discussion:-
Cost of Power Generation
Availability of nuclear fuel, breeder reactor.
Safety of nuclear plants.

24. Conclusion
In this we learned different construction methods of nuclear power
plants. By using these methods we can produce more power with
less stakeholders and if we use these types of advanced techniques
we can reduce pollution and we can be safe side.

25. Reference
 www.npcil.nic.in/main/all project
 Application of Advanced Construction Technologies to New Nuclear Power
Plants, MPR-2610(2004), prepared for the US Department of Energy
 INTERNATIONAL ATOMIC ENERGY AGENCY, Improving economics and
safety of water cooled reactors: Proven means and new approaches, TECDOC-
1290, IAEA, Vienna (2002).
 http://en.wikipedia.org/wiki/Nuclear_fission

26. THANK’S FOR YOUR ATTENTION!