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Nuclear Fusion and its future prospects
as a Primary source of Energy
Submitted in partial fulfilment of the requirements for the degree of
Bachelor of Technology
By
Kshitij Nishan
Register No. - 12130038
Semester- VII
Division of Mechanical Engineering
School of Engineering, Cochin University of Science and Technology, Kochi-22
Seminar Co-ordinator Head of Division
Dr. Joseph Alexander Dr. Biju Narayanan
COCHIN UNIVERSITY OF SCIENCE AND TECHNOLOGY
SCHOOL OF ENGINEERING
CERTIFICATE
This is to certify that the seminar report entitled
Nuclear Fusion and its future prospects
as a Primary source of Energy
was submitted by
Kshitij Nishan
of seventh semester, Division of Mechanical Engineering , School of Engineering,
Cochin University of Science and Technology during the year 2015.
Seminar Co-ordinator
Dr. Joseph Alexander
Head of Division
Dr. Biju Narayanan
ACKNOWLEDGEMENTS
It is my privilege to express my sincere gratitude and deep indebtedness to
people who helped me in completing this seminar successfully.
All glory and honours to God Almighty, who showered his grace upon me to
make this endeavour a success.
I am deeply grateful to Dr. G. Madhu, Principal of School of Engineering for
providing me the opportunity to complete my seminar.
I express my gratitude to Dr. Biju N, Head of Department of Mechanical
Engineering, School of Engineering for his valuable suggestions, advice and
encouragement throughout this seminar.
I am extremely grateful to Dr Joseph Alexander, associate professor of the
Division of Mechanical Engineering, School of Engineering, for the extensive
help and guidance for the completion of the seminar.
I also wish to express my gratitude to all my teaching and non teaching staff of
Mechanical Engineering Department for their valuable support and help. I
would like to thank my parents and friends for their support and valuable
suggestions.
Lastly, I express my sincere thanks to all those who directly or indirectly have
supported me in all the stages of the completion of this seminar.
Kshitij Nishan
ABSTRACT
This seminar deals with the future prospects of nuclear fusion as an alternative
source of energy. The current alternative sources like solar, wind and tidal
energies offer promising results but they can’t be used to power up the entire
planet because of many reasons. So there has to be some alternative source of
energy which will be lasting, non-polluting and cheaper. Fusion energy offers a
promising future in this field both to lighten up the world with its infinite
stocks and non polluting nature.
The main points of this seminar include how the process works and what’s its
viability.
Fusion power is the generation of energy by nuclear fusion. Fusion reactions
are high energy reactions in which two lighter atomic nuclei fuse to form a
heavier nucleus. When they combine, some of the mass is lost. This is
converted into energy, in accordance with the formula E = mc2
. Fusion power is
a research effort to try and harness this energy to power large scale cleaner
energy. It is also a major part of plasma physics research.
The seminar also deals with the safety related issues of the reaction and its
effects on the environment. While most of the odds support the process to
continue, some still disagree.
The Seminar will also deal about the advantages and the disadvantages of
using fusion as a future source of energy. The positives include the fact that it
will last forever and the entire energy crisis all over world will be fully
eradicated. Besides, its eco friendly produces large amounts of energy and
population can be settled around a reactor as there are no significant
radioactive decays.
Besides the seminar will also include the disadvantages which are a major
problem concerning the fact that the commercial use of this fusion energy has
not been started yet, and a lot of financial input has been put to use into the
experimentation.
CONTENTS
1. Introduction
2. Power Production
3. Need for Fusion Research
4. Proposedstructure of a Fusion Reactor
5. Safety and the Environment
6. Advantages and Disadvantages
7. Conclusion
8. References
1. Introduction
Fusion power is the generation of energy by nuclear fusion. Fusion reactions
are high energy reactions in which two lighter atomic nuclei fuse to form a
heavier nucleus. When they combine, some of the mass is lost. This is
converted into energy, in accordance with the formula E = mc2
. Fusion power is
a research effort to try and harness this energy to power large scale cleaner
energy. It is also a major part of plasma physics research. In largescale
commercial proposals, heat from the fusion reaction is used to operate a
steam turbine that drives electrical generators, as in existing fossil fuel and
nuclear fission power stations. Many different fusion concepts have come in
and out of vogue over the years. The current leading designs are the tokamak
and inertial confinement fusion (laser) approaches. These technologies are
not yet commercially viable. Currently, it takes more energy to initiate and
contain a fusion reaction, than the energy it produces. Scientists are currently
working to obtain better results.
The sun is a natural fusion reactor
Mechanism
Fusion reactions occur when two (or more) atomic nuclei come close enough
for the strong nuclear force pulling them together to exceed the electrostatic
force pushing them apart. This process takes light nuclei and forms a heavier
one, through a nuclear reaction. For nuclei lighter than iron-56 this
is exothermic and releases energy. For nuclei heavier than iron-56 this
is endothermic and requires an external source of energy. Hence, nuclei
smaller than iron-56 are more likely to fuse while those heavier than iron-56
are more likely to break apart.
To fuse, nuclei must be brought close enough together for the strong force to
act, which occurs only at very short distances. The electrostatic force keeping
them apart acts over long distances, so a significant amount of kinetic energy is
needed to overcome this "Coulomb barrier" before the reaction can take
place. There are several ways of doing this, including speeding up atoms in
a particle accelerator, or more commonly, heating them to very high
temperatures.
Once an atom is heated above its ionization energy, its electrons are stripped
away, leaving just the bare nucleus: the ion. The result is a hot cloud of ions
and the electrons formerly attached to them. This cloud is known as plasma.
Because the charges are separated, plasmas are electrically conductive and
magnetically controllable. Many fusion devices take advantage of this to
control the particles as they are being heated.
Theoretically, any atom could be fused, if enough pressure and temperature
was applied, and studies have been made of the required conditions to create
fusion conditions for a range of atoms. For a power plant, however, we are
currently limited to only the lightest elements. Hydrogen is ideal, because of its
small charge, it is the easiest atom to fuse. This reaction produces helium.
Plasma behaviour
Plasma can be made by fully ionizing a gas. Plasma is a fluid which conducts
electricity. In bulk, it is modelled using Magneto-hydrodynamics which is a
combination of the Navier-Stokes equations governing fluids
and Maxwell’s equations governing how magnetic and electric fields
behave. Fusion exploits several plasma properties, including:
Self-Organization Plasma conducts electric and magnetic fields. This means
that it can self-organize. Its motions can generate fields which can, in turn, self-
contain it.
Diamagnetic Plasma Plasma can generate its own internal magnetic field. This
can reject an externally applied magnetic field, making it diamagnetic.
Magnetic mirrors Plasma can be reflected when it moves from a low to high
density magnetic field.
Energy capture
There are several proposals for energy capture. The simplest is using a heat
cycle to heat a fluid with fusion reactions. It has been proposed to use the
neutrons generated by fusion to re-generate a spent fission fuel. In
addition, direct energy conversion, has been developed as a method to
maintain a voltage using the products of a fusion reaction. This has
demonstrated an energy capture efficiency of 48 percent.
Fuels
By firing particle beams at targets, many fusion reactions have been tested,
while the fuels considered for power have all been light elements like the
isotopes of hydrogen—deuterium and tritium. Other reactions like the
deuterium and Helium reaction or the Helium and Helium reactions would
require a supply of Helium. This can either come from other nuclear reactions
or from extraterrestrial sources. Finally, researchers hope to do the p-
11B reaction, because it does not directly produce neutrons, though side
reactions can.
Deuterium, Tritium
The easiest nuclear reaction, at the lowest energy, is:
2
D1 + 3
T1 → 4
He2 + 1
n0
This reaction is common in research, industrial and military applications,
usually as a convenient source of neutrons. Deuterium is a naturally
occurring isotope of hydrogen and is commonly available. The large mass ratio
of the hydrogen isotopes makes their separation easy compared to the
difficult uranium enrichment process. Tritium is a natural isotope of hydrogen,
but due to its short half-life of 12.32 years, is hard to find, store, produce, and
is expensive. Consequently, the deuterium-tritium fuel cycle requires
the breeding of tritium.
The reactant neutron is supplied by the D-T fusion reaction shown above, and
the one that has the greatest yield of energy. The reaction with 6
Li
is exothermic, providing a small energy gain for the reactor. The reaction
with 7
Li is endothermic but does not consume the neutron. At least some 7
Li
reactions are required to replace the neutrons lost to absorption by other
elements. Most reactor designs use the naturally occurring mix of lithium
isotopes.
Several drawbacks are commonly attributed to D-T fusion power:
1. It produces substantial amounts of neutrons that result in
the neutron activation of the reactor materials.
2. Only about 20% of the fusion energy yield appears in the form of
charged particles with the remainder carried off by neutrons, which
limits the extent to which direct energy conversion techniques
might be applied.
3. It requires the handling of the radioisotope tritium. Similar to
hydrogen, tritium is difficult to contain and may leak from reactors
in some quantity. Some estimates suggest that this would represent
a fairly large environmental release of radioactivity.
Deuterium
This is the second easiest fusion reaction, fusing deuteriumwith itself. The
reaction has two branches that occur with nearly equal probability:
D + D → T + 1
H
D + D → 3
He + n
This reaction is also common in research. The optimum energy to initiate this
reaction is 15 keV, only slightly higher than the optimum for the D-T reaction.
The first branch does not produce neutrons, but it does produce tritium, so
that a D-D reactor will not be completely tritium-free, even though it does not
require an input of tritium or lithium. Unless the tritons can be quickly
removed, most of the tritium produced would be burned before leaving the
reactor, which would reduce the handling of tritium, but would produce more
neutrons, some of which are very energetic. The neutron from the second
branch has an energy of only 2.45 MeV (0.393 pJ), whereas the neutron from
the D-T reaction has an energy of 14.1 MeV (2.26 pJ), resulting in a wider range
of isotope production and material damage. When the tritons are removed
quickly while allowing the 3
He to react, the fuel cycle is called "tritium
suppressed fusion". The removed tritium decays to 3
He with a 12.5 year half
life. By recycling the 3
He produced from the decay of tritium back into the
fusion reactor, the fusion reactor does not require materials resistant to fast
14.1 MeV (2.26 pJ) neutrons.
Assuming complete tritium burn-up, the reduction in the fraction of fusion
energy carried by neutrons would be only about 18%, so that the primary
advantage of the D-D fuel cycle is that tritium breeding would not be required.
Other advantages are independence fromscarce lithium resources and a
somewhat softer neutron spectrum. The disadvantage of D-D compared to D-T
is that the energy confinement time (at a given pressure) must be 30 times
longer and the power produced (at a given pressure and volume) would be 68
times less.
Assuming complete removal of tritium and recycling of 3
He, only 6% of the
fusion energy is carried by neutrons. The tritium-suppressed D-D fusion
requires an energy confinement that is 10 times longer compared to D-T and a
plasma temperature that is twice as high.
Deuterium, 3Helium
A second-generation approach to controlled fusion power involves
combining helium-3 (3
He) and deuterium (2
H):
D + 3
He → 4
He + 1
H
This reaction produces a helium-4 nucleus (4
He) and a high-energy proton. As
with the p-11
B aneutronic fusion fuel cycle, most of the reaction energy is
released as charged particles, reducing activation of the reactor housing and
potentially allowing more efficient energy harvesting (via any of several
speculative technologies). In practice, D-D side reactions produce a significant
number of neutrons, resulting in p-11
B being the preferred cycle for aneutronic
fusion.
Proton, Boron 11
If aneutronic fusion is the goal, then the most promising candidate may be the
Hydrogen-1 (proton)/boron reaction, which releases alpha (helium) particles,
but does not rely on neutron scattering for energy transfer.
1
H + 11
B → 3 4
He
Under reasonable assumptions, side reactions will result in about 0.1% of the
fusion power being carried by neutrons. At 123 keV, the optimum
temperature for this reaction is nearly ten times higher than that for the pure
hydrogen reactions, the energy confinement must be 500 times better than
that required for the D-T reaction, and the power density will be 2500 times
lower than for D-T.
Plasma Confinement
Confinement refers to all the conditions necessary to keep plasma dense and
hot long enough to undergo fusion. Some general principles are Equilibrium,
Stability and Conduction.
 Equilibrium: The forces acting on the plasma must be balanced for
containment. One exception is inertial confinement, where the relevant
physics must occur faster than the disassembly time.
 Stability: The plasma must be so constructed so that disturbances will not
lead to the plasma disassembling.
 Transport or conduction: The loss of material must be sufficiently slow. The
plasma carries off energy with it, so rapid loss of material will disrupt any
machines power balance. Material can be lost by transport into different
regions or conduction through a solid or liquid.
Types of plasmaconfinement:
1. Magnetic confinement
At the temperatures required for fusion, the fuel is heated to a plasma state. In
this state it has a very good electrical conductivity. This opens the possibility of
confining the plasma with magnetic fields. This is the case of magnetized
plasma, where the magnetic fields and plasma intermix. This is generally
known as magnetic confinement. The field lines put a Lorentz force on the
plasma. The forceworks perpendicular to the magnetic fields, so one problem
in magnetic confinement is preventing the plasma from leaking out the ends of
the field lines. A general measure of magnetic trapping in fusion is the beta
ratio:
Fig. Magnetic Confinement
Magnetic Mirror One example of magnetic confinement is with the magnetic
mirror effect. If a particle follows the field line and enters a region of higher
field strength, the particles can be reflected. There are several devices that try
to use this effect. The most famous was the magnetic mirror machines, which
was a series of large, expensive devices built at the Lawrence Livermore
National Laboratory from the 1960s to mid 1980s. Some other examples
include the magnetic bottles and Biconic cusp. Because the mirror machines
were straight, they had some advantages over a ring shape. First, mirrors
would easier to construct and maintain and second direct conversion energy
capture, was easier to implement. As the confinement achieved in experiments
was poor, this approach was abandoned.
Magnetic Loops Another example of magnetic confinement is to bend the field
lines back on themselves, either in circles or more commonly in
nested toroidal surfaces. The most highly developed system of this type is
the tokamak, with the stellarator being next most advanced, followed by
the Reversed field pinch. Compact toroids, especially the Field-Reversed
Configuration and the spheromak, attempt to combine the advantages of
toroidal magnetic surfaces with those of a simply connected (non-toroidal)
machine, resulting in a mechanically simpler and smaller confinement area.
2. Inertial confinement
Inertial confinement is the use of rapidly imploding shell to heat and confine
plasma. The shell is imploded using a direct laser blast (direct drive) or a
secondary x-ray blast (indirect drive) or heavy ion beams. Theoretically, fusion
using lasers would be done using tiny pellets of fuel that explode several times
a second. To induce the explosion, the pellet must be compressed to about 30
times solid density with energetic beams. If direct drive is used - the beams are
focused directly on the pellet - it can in principle be very efficient, but in
practice is difficult to obtain the needed uniformity. The alternative approach,
indirect drive, uses beams to heat a shell, and then the shell radiates x-rays,
which then implode the pellet. The beams are commonly laser beams, but
heavy and light ion beams and electron beams have all been investigated.
3. Electrostatic confinement
There are also electrostatic confinement fusion devices. These devices
confine ions using electrostatic fields. The best known is the Fusor. This device
has a cathode inside an anode wire cage. Positive ions fly towards the negative
inner cage, and are heated by the electric field in the process. If they miss the
inner cage they can collide and fuse. Ions typically hit the cathode, however,
creating prohibitory high conduction losses. Also, fusion rates in fusors are very
low due to competing physical effects, such as energy loss in the form of light
radiation. Designs have been proposed to avoid the problems associated with
the cage, by generating the field using a non-neutral cloud. These include a
plasma oscillating device, a penning trap and the polywell. The technology is
relatively immature, however, and many scientific and engineering questions
remain.
Fig. Inertial Confinement
2. Power Production
Three methods have been proposed so far for producing power using nuclear
fusion:
Steam turbines It has been proposed that steam turbines be used to convert
the heat from the fusion chamber into electricity. The heat is transferred into
a working fluid that turns into steam, driving electric generators.
Neutron blankets Deuterium and tritium fusion generates neutrons. This
varies by technique (NIF has a record of 3E14 neutrons per second while a
typical fusor produces 1E5 - 1E9 neutrons per second). It has been proposed to
use these neutrons as a way to regenerate spent fission fuel or as a way to
breed tritium from a liquid lithium blanket.
Direct conversion This is a method where the kinetic energy of a particle is
converted into voltage. Itwas firstsuggested by Richard F. Post in conjunction
with magnetic mirrors, in the late sixties. It has also been suggested for Field-
Reversed Configurations. The process takes the plasma, expands it, and
converts a large fraction of the random energy of the fusion products into
directed motion. The particles are then collected on electrodes at various large
electrical potentials. This method has demonstrated an experimental efficiency
of 48 percent.
3. Need for Fusion Research
• Ever increasing energy demand: The demand of energy will rise
continuously with the growing population.
• Limited fossil fuels: The fossil fuels are not going to last very long. Thus
we will need an alternate to this primary source of energy that can
satisfy the energy demands of this growing population.
• Global climate change: The fossil fuels have disturbed the balance of the
nature because of the release of the greenhouse gases. This can’t be
continued for long else there will be severe consequences.
• Limited scope of renewable energy: The renewable energy like solar,
wind and tidal energies are limited by many factors and thus will not be
able to satisfy the growing demand.
• High energy output by fusion: Fusion releases a very large amount of
energy and thus can be useful for a long time.
4. Proposed structure of a Fusion
reactor
Working of a fusion reactor
• The fusion reactor will heat a stream of deuterium and tritium fuel to
form high-temperature plasma. Itwill squeeze the plasma so that fusion
can take place.
• The lithium blankets outside the plasma reaction chamber will absorb
high-energy neutrons from the fusion reaction to make more tritium
fuel. The blankets will also get heated by the neutrons.
• The heat will be transferred by a water-cooling loop to a heat exchanger
to make steam.
• The steam will drive electrical turbines to produce electricity.
• The steam will be condensed back into water to absorb more heat from
the reactor in the heat exchanger
Material Selection for a fusion reactor:
1. Considerations
Any power plant using hot plasma, is going to have plasma facing walls. In even
the simplest plasma approaches, the material will get blasted with matter and
energy. This leads to a minimum list of considerations, including dealing with:
 A heating and cooling cycle, up to a 10 MW/m² thermal load.
 Neutron radiation, which over time leads to neutron
activation and embrittlement.
 High energy ions leaving at tens to hundreds of electronvolts.
 Alpha particles leaving at millions of electronvolts.
 Electrons leaving at high energy.
 Light radiation (IR, visible, UV, X-ray).
2. Durability
For long term use, each atom in the wall is expected to be hit by a neutron and
displaced about a hundred times before the material is replaced. High-energy
neutrons will produce hydrogen and helium by way of various nuclear
reactions that tends to form bubbles at grain boundaries and result in swelling,
blistering or embrittlement.
3. Selection
One can choose either a low-Z material, such as graphite or beryllium, or a
high-Z material, usually tungsten with molybdenum as a second choice. Use of
liquid metals (lithium, gallium, tin) has also been proposed, e.g., by injection of
1–5 mm thick streams flowing at 10 m/s on solid substrates.
If graphite is used, the gross erosion rates due to physical and
chemical sputtering would be many meters per year, so one must rely on
redeposition of the sputtered material. The location of the redeposition will
not exactly coincide with the location of the sputtering, so one is still left with
erosion rates that may be prohibitive. An even larger problem is the tritium co-
deposited with the redeposited graphite. The tritium inventory in graphite
layers and dust in a reactor could quickly build up to many kilograms,
representing a waste of resources and a serious radiological hazard in case of
an accident. The consensus of the fusion community seems to be that graphite,
although a very attractive material for fusion experiments cannot be the
primary PFC material in a commercial reactor.
The sputtering rate of tungsten by the plasma fuel ions is orders of magnitude
smaller than that of carbon, and tritium is much less incorporated into
redeposited tungsten, making this a more attractive choice. On the other hand,
tungsten impurities in plasma are much more damaging than carbon
impurities, and self-sputtering of tungsten can be high, so it will be necessary
to ensure that the plasma in contact with the tungsten is not too hot (a few
tens of eV rather than hundreds of eV). Tungsten also has disadvantages in
terms of eddy currents and melting in off-normal events, as well as some
radiological issues.
5. Safety and the Environment
Accident potential
Catastrophic accidents that release radioactivity to the environment or injury
to non-staff are not possible, unlike fission reactors. Nuclear fusion is very
unlike nuclear fission: fusion requires extremely precise and controlled
temperature, pressure and magnetic field parameters for any net energy to be
produced along with a far smaller amount of fuel. If a reactor suffers damage
or loses even a small degree of required control, fusion reactions and heat
generation would rapidly cease. Therefore, fusion reactors are considered
extremely safe.
Runaway reactions cannot occur in a fusion reactor. The plasma is burnt at
optimal conditions, and any significant change will quench the reactions. The
reaction process is so delicate that this level of safety is inherent. Although the
plasma in a fusion power plant is expected have a volume of 1,000 cubic
metres (35,000 cu ft) or more, the plasma density is low and the total amount
of fusion fuel in the vessel typically only a few grams. If the fuel supply is
closed, the reaction stops within seconds. In comparison, a fission reactor is
typically loaded with enough fuel for several years, and no additional fuel is
necessary to continue the reaction.
In the magnetic approach, strong fields are developed in coils that are held in
place mechanically by the reactor structure. Failure of this structure could
release this tension and allow the magnet to "explode" outward. The severity
of this event would be similar to any other industrial accident or
an MRI machine quench/explosion, and could be effectively stopped with
a containment building similar to those used in existing (fission) nuclear
generators. The laser-driven inertial approach is generally lower-stress.
Although failure of the reaction chamber is possible, simply stopping fuel
delivery would prevent any sort of catastrophic failure.
Effluents
The natural product of the fusion reaction is a small amount of helium, which is
completely harmless to life. Of more concern is tritium, which, like other
isotopes of hydrogen, is difficult to retain completely. During normal
operation, some amount of tritium will be continually released. There would
be no acute danger, but the cumulative effect on the world's population from a
fusion economy could be a matter of concern.
Although tritium is volatile and biologically active, the health risk posed by a
release is much lower than that of most radioactive contaminants, due to
tritium's short half-life (12.32 years), very low decay energy (~14.95 keV), and
the fact that it does not bio-accumulate (instead being cycled out of the body
as water, with a biological half-life of 7 to 14 days). Current ITER designs are
investigating total containment facilities for any tritium.
Waste management
The large flux of high-energy neutrons in a reactor will make the structural
materials radioactive. The radioactive inventory at shut-down may be
comparable to that of a fission reactor, but there are important differences.
The half-life of the radioisotopes produced by fusion tends to be less than
those from fission, so that the inventory decreases more rapidly. Unlike fission
reactors, whose waste remains radioactive for thousands of years, most of the
radioactive material in a fusion reactor would be the reactor core itself, which
would be dangerous for about 50 years, and low-level waste another 100.
Although this waste will be considerably more radioactive during those 50
years than fission waste, the very short half-life makes the process very
attractive, as the waste management is fairly straightforward. By 500 years the
material would have the same radio toxicity as coal ash.
In general terms, fusion reactors would create far less radioactive material
than a fission reactor, the material it would create is less damaging biologically,
and the radioactivity "burns off" within a time period that is well within
existing engineering capabilities for safe long-term waste storage.
Energy source
Fusion power commonly proposes the use of deuterium, an isotope of
hydrogen, as fuel and in many current designs also use lithium. Assuming a
fusion energy output equal to the 1995 global power output of about 100 EJ/yr
(= 1 × 1020
J/yr) and that this does not increase in the future, which is unlikely,
then the known current lithium reserves would last 3000 years. Lithium from
sea water would last 60 million years, however, and a more complicated fusion
process using only deuterium from sea water would have fuel for 150 billion
years. To put this in context, 150 billion years is close to 30 times the
remaining lifespan of the sun, and more than 10 times the estimated age of
the universe.
6. Advantages and Disadvantages
Advantages:
Fusion power would provide more energy for a given weight of fuel than any
fuel-consuming energy source currently in use, and the fuel itself
(primarily deuterium) exists abundantly in the Earth's ocean: about 1 in 6500
hydrogen atoms in seawater is deuterium. Although this may seem a low
proportion (about 0.015%), because nuclear fusion reactions are so much
more energetic than chemical combustion and seawater is easier to access and
more plentiful than fossil fuels, fusion could potentially supply the world's
energy needs for millions of years.
Despite being technically non-renewable, fusion power has many of the
benefits of renewable energy sources (such as being a long-term energy supply
and emitting non-greenhouse gases) as well as some of the benefits of the
resource-limited energy sources as hydrocarbons and nuclear fission
(without reprocessing). Like these currently dominant energy sources, fusion
could provide very high power-generation density and uninterrupted power
delivery (due to the fact that it is not dependent on the weather, unlike wind
and solar power).
Another aspect of fusion energy is that the cost of production does not suffer
from diseconomies of scale. The cost of water and wind energy, for example,
goes up as the optimal locations are developed first, while further generators
must be sited in less ideal conditions. With fusion energy the production cost
will not increase much even if large numbers of plants are built, because the
raw resource (seawater) is abundant and widespread.
Some problems that are expected to be an issue in this century, such as fresh
water shortages, can alternatively be regarded as problems of energy supply.
For example, desalination plants, seawater can be purified
through distillation or reverse osmosis. Nonetheless, these processes are
energy intensive. Even if the first fusion plants are not competitive with
alternative sources, fusion could still become competitive if large-scale
desalination requires more power than the alternatives are able to provide.
A scenario has been presented of the effect of the commercialization of fusion
power on the future of human civilization. ITER and later Demo are envisioned
to bring online the first commercial nuclear fusion energy reactor by 2050.
Using this as the starting point and the history of the uptake of nuclear fission
reactors as a guide, the scenario depicts a rapid take up of nuclear fusion
energy starting after the middle of this century.
Fusion power could be used in interstellar space, where solar energy is not
available.
Disadvantages
The disadvantages of this system of power generation arevery few. But the
most important is the fact that its commercial use has not been started yet
and a large investment has already been made to researches.
The material for setups has to be worked upon so that it can take the
excessive temperatures produced during the process. Thus specialized
materials have to be developed and used.
7. Conclusion
Considering the fact that with the growing population and the growing
dependencies of humanity on energy sources, the current sources of energy
like fossil fuels are not going to last long. And the alternative sources of energy
like solar and wind energies will not be sufficient enough to deal with the
demands. Thus nuclear power is the future alternative to today’s primary
sources of energy and will help in preserving nature as well. So if fusion turns
out to be useful, all our investments will become worthwhile. Humanity will
have a cleaner source of energy which will last for millions of years.
8. References
• Wikipedia
• energy.wesrch.com
• lasma hysics on nement Transport and ollec ve ects By
ndreas inklage Thomas linger Gerrit Marx – 2005
• www.world-nuclear.org/info/Current-and-Future-Generation/Nuclear-
Fusion-Power

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Nuclear fusion seminar report

  • 1. Nuclear Fusion and its future prospects as a Primary source of Energy Submitted in partial fulfilment of the requirements for the degree of Bachelor of Technology By Kshitij Nishan Register No. - 12130038 Semester- VII Division of Mechanical Engineering School of Engineering, Cochin University of Science and Technology, Kochi-22 Seminar Co-ordinator Head of Division Dr. Joseph Alexander Dr. Biju Narayanan
  • 2. COCHIN UNIVERSITY OF SCIENCE AND TECHNOLOGY SCHOOL OF ENGINEERING CERTIFICATE This is to certify that the seminar report entitled Nuclear Fusion and its future prospects as a Primary source of Energy was submitted by Kshitij Nishan of seventh semester, Division of Mechanical Engineering , School of Engineering, Cochin University of Science and Technology during the year 2015. Seminar Co-ordinator Dr. Joseph Alexander Head of Division Dr. Biju Narayanan
  • 3. ACKNOWLEDGEMENTS It is my privilege to express my sincere gratitude and deep indebtedness to people who helped me in completing this seminar successfully. All glory and honours to God Almighty, who showered his grace upon me to make this endeavour a success. I am deeply grateful to Dr. G. Madhu, Principal of School of Engineering for providing me the opportunity to complete my seminar. I express my gratitude to Dr. Biju N, Head of Department of Mechanical Engineering, School of Engineering for his valuable suggestions, advice and encouragement throughout this seminar. I am extremely grateful to Dr Joseph Alexander, associate professor of the Division of Mechanical Engineering, School of Engineering, for the extensive help and guidance for the completion of the seminar. I also wish to express my gratitude to all my teaching and non teaching staff of Mechanical Engineering Department for their valuable support and help. I would like to thank my parents and friends for their support and valuable suggestions. Lastly, I express my sincere thanks to all those who directly or indirectly have supported me in all the stages of the completion of this seminar. Kshitij Nishan
  • 4. ABSTRACT This seminar deals with the future prospects of nuclear fusion as an alternative source of energy. The current alternative sources like solar, wind and tidal energies offer promising results but they can’t be used to power up the entire planet because of many reasons. So there has to be some alternative source of energy which will be lasting, non-polluting and cheaper. Fusion energy offers a promising future in this field both to lighten up the world with its infinite stocks and non polluting nature. The main points of this seminar include how the process works and what’s its viability. Fusion power is the generation of energy by nuclear fusion. Fusion reactions are high energy reactions in which two lighter atomic nuclei fuse to form a heavier nucleus. When they combine, some of the mass is lost. This is converted into energy, in accordance with the formula E = mc2 . Fusion power is a research effort to try and harness this energy to power large scale cleaner energy. It is also a major part of plasma physics research. The seminar also deals with the safety related issues of the reaction and its effects on the environment. While most of the odds support the process to continue, some still disagree. The Seminar will also deal about the advantages and the disadvantages of using fusion as a future source of energy. The positives include the fact that it will last forever and the entire energy crisis all over world will be fully eradicated. Besides, its eco friendly produces large amounts of energy and population can be settled around a reactor as there are no significant radioactive decays. Besides the seminar will also include the disadvantages which are a major problem concerning the fact that the commercial use of this fusion energy has not been started yet, and a lot of financial input has been put to use into the experimentation.
  • 5. CONTENTS 1. Introduction 2. Power Production 3. Need for Fusion Research 4. Proposedstructure of a Fusion Reactor 5. Safety and the Environment 6. Advantages and Disadvantages 7. Conclusion 8. References
  • 6. 1. Introduction Fusion power is the generation of energy by nuclear fusion. Fusion reactions are high energy reactions in which two lighter atomic nuclei fuse to form a heavier nucleus. When they combine, some of the mass is lost. This is converted into energy, in accordance with the formula E = mc2 . Fusion power is a research effort to try and harness this energy to power large scale cleaner energy. It is also a major part of plasma physics research. In largescale commercial proposals, heat from the fusion reaction is used to operate a steam turbine that drives electrical generators, as in existing fossil fuel and nuclear fission power stations. Many different fusion concepts have come in and out of vogue over the years. The current leading designs are the tokamak and inertial confinement fusion (laser) approaches. These technologies are not yet commercially viable. Currently, it takes more energy to initiate and contain a fusion reaction, than the energy it produces. Scientists are currently working to obtain better results. The sun is a natural fusion reactor
  • 7. Mechanism Fusion reactions occur when two (or more) atomic nuclei come close enough for the strong nuclear force pulling them together to exceed the electrostatic force pushing them apart. This process takes light nuclei and forms a heavier one, through a nuclear reaction. For nuclei lighter than iron-56 this is exothermic and releases energy. For nuclei heavier than iron-56 this is endothermic and requires an external source of energy. Hence, nuclei smaller than iron-56 are more likely to fuse while those heavier than iron-56 are more likely to break apart. To fuse, nuclei must be brought close enough together for the strong force to act, which occurs only at very short distances. The electrostatic force keeping them apart acts over long distances, so a significant amount of kinetic energy is needed to overcome this "Coulomb barrier" before the reaction can take place. There are several ways of doing this, including speeding up atoms in a particle accelerator, or more commonly, heating them to very high temperatures. Once an atom is heated above its ionization energy, its electrons are stripped away, leaving just the bare nucleus: the ion. The result is a hot cloud of ions and the electrons formerly attached to them. This cloud is known as plasma. Because the charges are separated, plasmas are electrically conductive and magnetically controllable. Many fusion devices take advantage of this to control the particles as they are being heated. Theoretically, any atom could be fused, if enough pressure and temperature was applied, and studies have been made of the required conditions to create fusion conditions for a range of atoms. For a power plant, however, we are currently limited to only the lightest elements. Hydrogen is ideal, because of its small charge, it is the easiest atom to fuse. This reaction produces helium.
  • 8. Plasma behaviour Plasma can be made by fully ionizing a gas. Plasma is a fluid which conducts electricity. In bulk, it is modelled using Magneto-hydrodynamics which is a combination of the Navier-Stokes equations governing fluids and Maxwell’s equations governing how magnetic and electric fields behave. Fusion exploits several plasma properties, including: Self-Organization Plasma conducts electric and magnetic fields. This means that it can self-organize. Its motions can generate fields which can, in turn, self- contain it. Diamagnetic Plasma Plasma can generate its own internal magnetic field. This can reject an externally applied magnetic field, making it diamagnetic. Magnetic mirrors Plasma can be reflected when it moves from a low to high density magnetic field. Energy capture There are several proposals for energy capture. The simplest is using a heat cycle to heat a fluid with fusion reactions. It has been proposed to use the neutrons generated by fusion to re-generate a spent fission fuel. In addition, direct energy conversion, has been developed as a method to maintain a voltage using the products of a fusion reaction. This has demonstrated an energy capture efficiency of 48 percent. Fuels By firing particle beams at targets, many fusion reactions have been tested, while the fuels considered for power have all been light elements like the isotopes of hydrogen—deuterium and tritium. Other reactions like the deuterium and Helium reaction or the Helium and Helium reactions would require a supply of Helium. This can either come from other nuclear reactions or from extraterrestrial sources. Finally, researchers hope to do the p- 11B reaction, because it does not directly produce neutrons, though side reactions can.
  • 9. Deuterium, Tritium The easiest nuclear reaction, at the lowest energy, is: 2 D1 + 3 T1 → 4 He2 + 1 n0 This reaction is common in research, industrial and military applications, usually as a convenient source of neutrons. Deuterium is a naturally occurring isotope of hydrogen and is commonly available. The large mass ratio of the hydrogen isotopes makes their separation easy compared to the difficult uranium enrichment process. Tritium is a natural isotope of hydrogen, but due to its short half-life of 12.32 years, is hard to find, store, produce, and is expensive. Consequently, the deuterium-tritium fuel cycle requires the breeding of tritium. The reactant neutron is supplied by the D-T fusion reaction shown above, and the one that has the greatest yield of energy. The reaction with 6 Li is exothermic, providing a small energy gain for the reactor. The reaction with 7 Li is endothermic but does not consume the neutron. At least some 7 Li reactions are required to replace the neutrons lost to absorption by other elements. Most reactor designs use the naturally occurring mix of lithium isotopes. Several drawbacks are commonly attributed to D-T fusion power: 1. It produces substantial amounts of neutrons that result in the neutron activation of the reactor materials. 2. Only about 20% of the fusion energy yield appears in the form of charged particles with the remainder carried off by neutrons, which limits the extent to which direct energy conversion techniques might be applied. 3. It requires the handling of the radioisotope tritium. Similar to hydrogen, tritium is difficult to contain and may leak from reactors in some quantity. Some estimates suggest that this would represent a fairly large environmental release of radioactivity.
  • 10. Deuterium This is the second easiest fusion reaction, fusing deuteriumwith itself. The reaction has two branches that occur with nearly equal probability: D + D → T + 1 H D + D → 3 He + n This reaction is also common in research. The optimum energy to initiate this reaction is 15 keV, only slightly higher than the optimum for the D-T reaction. The first branch does not produce neutrons, but it does produce tritium, so that a D-D reactor will not be completely tritium-free, even though it does not require an input of tritium or lithium. Unless the tritons can be quickly removed, most of the tritium produced would be burned before leaving the reactor, which would reduce the handling of tritium, but would produce more neutrons, some of which are very energetic. The neutron from the second branch has an energy of only 2.45 MeV (0.393 pJ), whereas the neutron from the D-T reaction has an energy of 14.1 MeV (2.26 pJ), resulting in a wider range of isotope production and material damage. When the tritons are removed quickly while allowing the 3 He to react, the fuel cycle is called "tritium suppressed fusion". The removed tritium decays to 3 He with a 12.5 year half life. By recycling the 3 He produced from the decay of tritium back into the fusion reactor, the fusion reactor does not require materials resistant to fast 14.1 MeV (2.26 pJ) neutrons. Assuming complete tritium burn-up, the reduction in the fraction of fusion energy carried by neutrons would be only about 18%, so that the primary advantage of the D-D fuel cycle is that tritium breeding would not be required. Other advantages are independence fromscarce lithium resources and a somewhat softer neutron spectrum. The disadvantage of D-D compared to D-T is that the energy confinement time (at a given pressure) must be 30 times longer and the power produced (at a given pressure and volume) would be 68 times less. Assuming complete removal of tritium and recycling of 3 He, only 6% of the fusion energy is carried by neutrons. The tritium-suppressed D-D fusion requires an energy confinement that is 10 times longer compared to D-T and a plasma temperature that is twice as high.
  • 11. Deuterium, 3Helium A second-generation approach to controlled fusion power involves combining helium-3 (3 He) and deuterium (2 H): D + 3 He → 4 He + 1 H This reaction produces a helium-4 nucleus (4 He) and a high-energy proton. As with the p-11 B aneutronic fusion fuel cycle, most of the reaction energy is released as charged particles, reducing activation of the reactor housing and potentially allowing more efficient energy harvesting (via any of several speculative technologies). In practice, D-D side reactions produce a significant number of neutrons, resulting in p-11 B being the preferred cycle for aneutronic fusion. Proton, Boron 11 If aneutronic fusion is the goal, then the most promising candidate may be the Hydrogen-1 (proton)/boron reaction, which releases alpha (helium) particles, but does not rely on neutron scattering for energy transfer. 1 H + 11 B → 3 4 He Under reasonable assumptions, side reactions will result in about 0.1% of the fusion power being carried by neutrons. At 123 keV, the optimum temperature for this reaction is nearly ten times higher than that for the pure hydrogen reactions, the energy confinement must be 500 times better than that required for the D-T reaction, and the power density will be 2500 times lower than for D-T.
  • 12. Plasma Confinement Confinement refers to all the conditions necessary to keep plasma dense and hot long enough to undergo fusion. Some general principles are Equilibrium, Stability and Conduction.  Equilibrium: The forces acting on the plasma must be balanced for containment. One exception is inertial confinement, where the relevant physics must occur faster than the disassembly time.  Stability: The plasma must be so constructed so that disturbances will not lead to the plasma disassembling.  Transport or conduction: The loss of material must be sufficiently slow. The plasma carries off energy with it, so rapid loss of material will disrupt any machines power balance. Material can be lost by transport into different regions or conduction through a solid or liquid. Types of plasmaconfinement: 1. Magnetic confinement At the temperatures required for fusion, the fuel is heated to a plasma state. In this state it has a very good electrical conductivity. This opens the possibility of confining the plasma with magnetic fields. This is the case of magnetized plasma, where the magnetic fields and plasma intermix. This is generally known as magnetic confinement. The field lines put a Lorentz force on the plasma. The forceworks perpendicular to the magnetic fields, so one problem in magnetic confinement is preventing the plasma from leaking out the ends of the field lines. A general measure of magnetic trapping in fusion is the beta ratio: Fig. Magnetic Confinement
  • 13. Magnetic Mirror One example of magnetic confinement is with the magnetic mirror effect. If a particle follows the field line and enters a region of higher field strength, the particles can be reflected. There are several devices that try to use this effect. The most famous was the magnetic mirror machines, which was a series of large, expensive devices built at the Lawrence Livermore National Laboratory from the 1960s to mid 1980s. Some other examples include the magnetic bottles and Biconic cusp. Because the mirror machines were straight, they had some advantages over a ring shape. First, mirrors would easier to construct and maintain and second direct conversion energy capture, was easier to implement. As the confinement achieved in experiments was poor, this approach was abandoned. Magnetic Loops Another example of magnetic confinement is to bend the field lines back on themselves, either in circles or more commonly in nested toroidal surfaces. The most highly developed system of this type is the tokamak, with the stellarator being next most advanced, followed by the Reversed field pinch. Compact toroids, especially the Field-Reversed Configuration and the spheromak, attempt to combine the advantages of toroidal magnetic surfaces with those of a simply connected (non-toroidal) machine, resulting in a mechanically simpler and smaller confinement area. 2. Inertial confinement Inertial confinement is the use of rapidly imploding shell to heat and confine plasma. The shell is imploded using a direct laser blast (direct drive) or a secondary x-ray blast (indirect drive) or heavy ion beams. Theoretically, fusion using lasers would be done using tiny pellets of fuel that explode several times a second. To induce the explosion, the pellet must be compressed to about 30 times solid density with energetic beams. If direct drive is used - the beams are focused directly on the pellet - it can in principle be very efficient, but in practice is difficult to obtain the needed uniformity. The alternative approach, indirect drive, uses beams to heat a shell, and then the shell radiates x-rays, which then implode the pellet. The beams are commonly laser beams, but heavy and light ion beams and electron beams have all been investigated. 3. Electrostatic confinement There are also electrostatic confinement fusion devices. These devices confine ions using electrostatic fields. The best known is the Fusor. This device has a cathode inside an anode wire cage. Positive ions fly towards the negative inner cage, and are heated by the electric field in the process. If they miss the inner cage they can collide and fuse. Ions typically hit the cathode, however,
  • 14. creating prohibitory high conduction losses. Also, fusion rates in fusors are very low due to competing physical effects, such as energy loss in the form of light radiation. Designs have been proposed to avoid the problems associated with the cage, by generating the field using a non-neutral cloud. These include a plasma oscillating device, a penning trap and the polywell. The technology is relatively immature, however, and many scientific and engineering questions remain. Fig. Inertial Confinement
  • 15. 2. Power Production Three methods have been proposed so far for producing power using nuclear fusion: Steam turbines It has been proposed that steam turbines be used to convert the heat from the fusion chamber into electricity. The heat is transferred into a working fluid that turns into steam, driving electric generators. Neutron blankets Deuterium and tritium fusion generates neutrons. This varies by technique (NIF has a record of 3E14 neutrons per second while a typical fusor produces 1E5 - 1E9 neutrons per second). It has been proposed to use these neutrons as a way to regenerate spent fission fuel or as a way to breed tritium from a liquid lithium blanket. Direct conversion This is a method where the kinetic energy of a particle is converted into voltage. Itwas firstsuggested by Richard F. Post in conjunction with magnetic mirrors, in the late sixties. It has also been suggested for Field- Reversed Configurations. The process takes the plasma, expands it, and converts a large fraction of the random energy of the fusion products into directed motion. The particles are then collected on electrodes at various large electrical potentials. This method has demonstrated an experimental efficiency of 48 percent.
  • 16. 3. Need for Fusion Research • Ever increasing energy demand: The demand of energy will rise continuously with the growing population. • Limited fossil fuels: The fossil fuels are not going to last very long. Thus we will need an alternate to this primary source of energy that can satisfy the energy demands of this growing population. • Global climate change: The fossil fuels have disturbed the balance of the nature because of the release of the greenhouse gases. This can’t be continued for long else there will be severe consequences. • Limited scope of renewable energy: The renewable energy like solar, wind and tidal energies are limited by many factors and thus will not be able to satisfy the growing demand. • High energy output by fusion: Fusion releases a very large amount of energy and thus can be useful for a long time.
  • 17. 4. Proposed structure of a Fusion reactor Working of a fusion reactor • The fusion reactor will heat a stream of deuterium and tritium fuel to form high-temperature plasma. Itwill squeeze the plasma so that fusion can take place. • The lithium blankets outside the plasma reaction chamber will absorb high-energy neutrons from the fusion reaction to make more tritium fuel. The blankets will also get heated by the neutrons. • The heat will be transferred by a water-cooling loop to a heat exchanger to make steam. • The steam will drive electrical turbines to produce electricity. • The steam will be condensed back into water to absorb more heat from the reactor in the heat exchanger
  • 18. Material Selection for a fusion reactor: 1. Considerations Any power plant using hot plasma, is going to have plasma facing walls. In even the simplest plasma approaches, the material will get blasted with matter and energy. This leads to a minimum list of considerations, including dealing with:  A heating and cooling cycle, up to a 10 MW/m² thermal load.  Neutron radiation, which over time leads to neutron activation and embrittlement.  High energy ions leaving at tens to hundreds of electronvolts.  Alpha particles leaving at millions of electronvolts.  Electrons leaving at high energy.  Light radiation (IR, visible, UV, X-ray). 2. Durability For long term use, each atom in the wall is expected to be hit by a neutron and displaced about a hundred times before the material is replaced. High-energy neutrons will produce hydrogen and helium by way of various nuclear reactions that tends to form bubbles at grain boundaries and result in swelling, blistering or embrittlement. 3. Selection One can choose either a low-Z material, such as graphite or beryllium, or a high-Z material, usually tungsten with molybdenum as a second choice. Use of liquid metals (lithium, gallium, tin) has also been proposed, e.g., by injection of 1–5 mm thick streams flowing at 10 m/s on solid substrates. If graphite is used, the gross erosion rates due to physical and chemical sputtering would be many meters per year, so one must rely on redeposition of the sputtered material. The location of the redeposition will not exactly coincide with the location of the sputtering, so one is still left with erosion rates that may be prohibitive. An even larger problem is the tritium co- deposited with the redeposited graphite. The tritium inventory in graphite layers and dust in a reactor could quickly build up to many kilograms, representing a waste of resources and a serious radiological hazard in case of
  • 19. an accident. The consensus of the fusion community seems to be that graphite, although a very attractive material for fusion experiments cannot be the primary PFC material in a commercial reactor. The sputtering rate of tungsten by the plasma fuel ions is orders of magnitude smaller than that of carbon, and tritium is much less incorporated into redeposited tungsten, making this a more attractive choice. On the other hand, tungsten impurities in plasma are much more damaging than carbon impurities, and self-sputtering of tungsten can be high, so it will be necessary to ensure that the plasma in contact with the tungsten is not too hot (a few tens of eV rather than hundreds of eV). Tungsten also has disadvantages in terms of eddy currents and melting in off-normal events, as well as some radiological issues.
  • 20. 5. Safety and the Environment Accident potential Catastrophic accidents that release radioactivity to the environment or injury to non-staff are not possible, unlike fission reactors. Nuclear fusion is very unlike nuclear fission: fusion requires extremely precise and controlled temperature, pressure and magnetic field parameters for any net energy to be produced along with a far smaller amount of fuel. If a reactor suffers damage or loses even a small degree of required control, fusion reactions and heat generation would rapidly cease. Therefore, fusion reactors are considered extremely safe. Runaway reactions cannot occur in a fusion reactor. The plasma is burnt at optimal conditions, and any significant change will quench the reactions. The reaction process is so delicate that this level of safety is inherent. Although the plasma in a fusion power plant is expected have a volume of 1,000 cubic metres (35,000 cu ft) or more, the plasma density is low and the total amount of fusion fuel in the vessel typically only a few grams. If the fuel supply is closed, the reaction stops within seconds. In comparison, a fission reactor is typically loaded with enough fuel for several years, and no additional fuel is necessary to continue the reaction. In the magnetic approach, strong fields are developed in coils that are held in place mechanically by the reactor structure. Failure of this structure could release this tension and allow the magnet to "explode" outward. The severity of this event would be similar to any other industrial accident or an MRI machine quench/explosion, and could be effectively stopped with a containment building similar to those used in existing (fission) nuclear generators. The laser-driven inertial approach is generally lower-stress. Although failure of the reaction chamber is possible, simply stopping fuel delivery would prevent any sort of catastrophic failure. Effluents The natural product of the fusion reaction is a small amount of helium, which is completely harmless to life. Of more concern is tritium, which, like other isotopes of hydrogen, is difficult to retain completely. During normal operation, some amount of tritium will be continually released. There would be no acute danger, but the cumulative effect on the world's population from a fusion economy could be a matter of concern.
  • 21. Although tritium is volatile and biologically active, the health risk posed by a release is much lower than that of most radioactive contaminants, due to tritium's short half-life (12.32 years), very low decay energy (~14.95 keV), and the fact that it does not bio-accumulate (instead being cycled out of the body as water, with a biological half-life of 7 to 14 days). Current ITER designs are investigating total containment facilities for any tritium. Waste management The large flux of high-energy neutrons in a reactor will make the structural materials radioactive. The radioactive inventory at shut-down may be comparable to that of a fission reactor, but there are important differences. The half-life of the radioisotopes produced by fusion tends to be less than those from fission, so that the inventory decreases more rapidly. Unlike fission reactors, whose waste remains radioactive for thousands of years, most of the radioactive material in a fusion reactor would be the reactor core itself, which would be dangerous for about 50 years, and low-level waste another 100. Although this waste will be considerably more radioactive during those 50 years than fission waste, the very short half-life makes the process very attractive, as the waste management is fairly straightforward. By 500 years the material would have the same radio toxicity as coal ash. In general terms, fusion reactors would create far less radioactive material than a fission reactor, the material it would create is less damaging biologically, and the radioactivity "burns off" within a time period that is well within existing engineering capabilities for safe long-term waste storage. Energy source Fusion power commonly proposes the use of deuterium, an isotope of hydrogen, as fuel and in many current designs also use lithium. Assuming a fusion energy output equal to the 1995 global power output of about 100 EJ/yr (= 1 × 1020 J/yr) and that this does not increase in the future, which is unlikely, then the known current lithium reserves would last 3000 years. Lithium from sea water would last 60 million years, however, and a more complicated fusion process using only deuterium from sea water would have fuel for 150 billion years. To put this in context, 150 billion years is close to 30 times the remaining lifespan of the sun, and more than 10 times the estimated age of the universe.
  • 22. 6. Advantages and Disadvantages Advantages: Fusion power would provide more energy for a given weight of fuel than any fuel-consuming energy source currently in use, and the fuel itself (primarily deuterium) exists abundantly in the Earth's ocean: about 1 in 6500 hydrogen atoms in seawater is deuterium. Although this may seem a low proportion (about 0.015%), because nuclear fusion reactions are so much more energetic than chemical combustion and seawater is easier to access and more plentiful than fossil fuels, fusion could potentially supply the world's energy needs for millions of years. Despite being technically non-renewable, fusion power has many of the benefits of renewable energy sources (such as being a long-term energy supply and emitting non-greenhouse gases) as well as some of the benefits of the resource-limited energy sources as hydrocarbons and nuclear fission (without reprocessing). Like these currently dominant energy sources, fusion could provide very high power-generation density and uninterrupted power delivery (due to the fact that it is not dependent on the weather, unlike wind and solar power). Another aspect of fusion energy is that the cost of production does not suffer from diseconomies of scale. The cost of water and wind energy, for example, goes up as the optimal locations are developed first, while further generators must be sited in less ideal conditions. With fusion energy the production cost will not increase much even if large numbers of plants are built, because the raw resource (seawater) is abundant and widespread. Some problems that are expected to be an issue in this century, such as fresh water shortages, can alternatively be regarded as problems of energy supply. For example, desalination plants, seawater can be purified
  • 23. through distillation or reverse osmosis. Nonetheless, these processes are energy intensive. Even if the first fusion plants are not competitive with alternative sources, fusion could still become competitive if large-scale desalination requires more power than the alternatives are able to provide. A scenario has been presented of the effect of the commercialization of fusion power on the future of human civilization. ITER and later Demo are envisioned to bring online the first commercial nuclear fusion energy reactor by 2050. Using this as the starting point and the history of the uptake of nuclear fission reactors as a guide, the scenario depicts a rapid take up of nuclear fusion energy starting after the middle of this century. Fusion power could be used in interstellar space, where solar energy is not available. Disadvantages The disadvantages of this system of power generation arevery few. But the most important is the fact that its commercial use has not been started yet and a large investment has already been made to researches. The material for setups has to be worked upon so that it can take the excessive temperatures produced during the process. Thus specialized materials have to be developed and used.
  • 24. 7. Conclusion Considering the fact that with the growing population and the growing dependencies of humanity on energy sources, the current sources of energy like fossil fuels are not going to last long. And the alternative sources of energy like solar and wind energies will not be sufficient enough to deal with the demands. Thus nuclear power is the future alternative to today’s primary sources of energy and will help in preserving nature as well. So if fusion turns out to be useful, all our investments will become worthwhile. Humanity will have a cleaner source of energy which will last for millions of years.
  • 25. 8. References • Wikipedia • energy.wesrch.com • lasma hysics on nement Transport and ollec ve ects By ndreas inklage Thomas linger Gerrit Marx – 2005 • www.world-nuclear.org/info/Current-and-Future-Generation/Nuclear- Fusion-Power