Energy Conversion
Energy Conversion Using Steam
The combustion of coal, gas or oil in boilers produces steam, at high temperatures and pressures, which is passed through steam turbines. Nuclear fission can
also provide energy to produce steam for turbines. Axial-flow turbines are generally used with several cylinders, containing steam of reducing pressure, on the
same shaft.
A steam power-station operates on the Rankine cycle, modified to include superheating, feed-water heating, and steam reheating. High efficiency is achieved by the
use of steam at the maximum possible pressure and temperature. Also, for turbines
to be constructed economically, the larger the size the less the capital cost per unit of
power output. As a result, turbo-generator sets of 500 MW and more have been
used. With steam turbines above 100 MW, the efficiency is increased by reheating
the steam, using an external heater, after it has been partially expanded. The
reheated steam is then returned to the turbine where it is expanded through the final
stages of blading.
In coal-fired stations, coal is conveyed to a mill and crushed into fine powder, that
is pulverized. The pulverized fuel is blown into the boiler where it mixes with a
supply of air for combustion. The exhaust steam from the low pressure (L.P.) turbine is cooled to form condensate by the passage through the condenser of large
quantities of sea- or river-water. Cooling towers are used where the station is
located inland or if there is concern over the environmental effects of raising the
temperature of the sea- or river-water.
Despite continual advances in the design of boilers and in the development of
improved materials, the nature of the steam cycle is such that vast quantities of
heat are lost in the condensate cooling system and to the atmosphere. Advances
in design and materials in the last few years have increased the thermal efficiencies of new coal stations to approaching 40%. If a use can be found for the
remaining 60% of energy rejected as heat, fairly close to the power station,
forming a Combined Heat and Power (or Co-generation) system then this is
clearly desirable.
Energy Conversion Using Water
Perhaps the oldest form of energy conversion is by the use of water power. In a
hydroelectric station the energy is obtained free of cost. This attractive feature has
always been somewhat offset by the very high capital cost of construction, especially
of the civil engineering works. Unfortunately, the geographical conditions necessary
for hydro-generation are not commonly found, especially in Britain. In most developed countries, all the suitable hydroelectric sites are already fully utilized. There
still exists great hydroelectric potential in many developing countries but large
hydro schemes, particularly those with large reservoirs, have a significant impact
on the environment and the local population.
The difference in height between the upper reservoir and the level of the turbines
or outflow is known as the head. The water falling through this head gains energy
which it then imparts to the turbine blades. Impulse turbines use a jet of water at
atmospheric pressure while in reaction turbines the pressure drops across the runner imparts significant energy.
Particular types of turbine are associated with the various heights or heads of
water level above the turbines. These are:
- Pelton: This is used for heads of 150–1500 m and consists of a bucket wheel rotor
with water jets from adjustable flow nozzles.
- Francis: This is used for heads of 50–500 m with the water flow within the turbine
following a spiral path.
- Kaplan: This is used for run-of-river stations with heads of up to 60 m. This type
has an axial-flow rotor with variable-pitch blades.
Typical efficiency curves for each type of turbine are shown in Figure 1.5.
Hydroelectric plant has the ability to start up quickly and the advantage that no
energy losses are incurred when at a standstill. It has great advantages, therefore,
for power generation because of this ability to meet peak loads at minimum operating cost, working in conjunction with thermal stations – see Figure. By using
remote control of the hydro sets, the time from the instruction to start up to the
actual connection to the power network can be as short as 3 minutes.
The power available from a hydro scheme is given by
P = rgQH (W)
where
Q = flow rate (m3/s) through the turbine;
r = density of water (1000 kg/m3);
g = acceleration due to gravity (9.81 m/s2);
H = head, that is height of upper water level above the lower (m).
Substituting,
P= 9.81QH (kW)
Gas Turbines
With the increasing availability of natural gas (methane) and its low emissions
and competitive price, prime movers based on the gas turbine cycle are being used
increasingly. This thermodynamic cycle involves burning the fuel in the compressed
working fluid (air) and is used in aircraft with kerosene as the fuel and for electricity
generation with natural gas (methane). Because of the high temperatures obtained,
the efficiency of a gas turbine is comparable to that of a steam turbine, with the additional advantage that there is still sufficient heat in the gas-turbine exhaust to raise
steam in a conventional boiler to drive a steam turbine coupled to another electricity
generator. This is known as a combined-cycle gas-turbine (CCGT) plant, a schematic
layout of which is shown in Figure 1.6. Combined efficiencies of new CCGT generators now approach 60%.
The advantages of CCGT plant are the high efficiency possible with large units
and, for smaller units, the fast start up and shut down (2–3 min for the gas turbine,
20 min for the steam turbine), the flexibility possible for load following, the comparative speed of installation because of its modular nature and factory-supplied units, and its ability to run on light oil (from local storage tanks) if the gas supply is interrupted. Modern installations are fully automated and require only a few operators
to maintain 24 hour running or to supply peak load, if needed.
Nuclear Power
Energy is obtained from the fission reaction which involves the splitting of the nuclei of uranium atoms. Compared with chemical reactions, very large amounts of energy are released per atomic event. Uranium metal extracted from the base ore consists mainly of two isotopes, 238U (99.3% by weight) and 235U (0.7%). Only 235U is fissile, that is when struck by slow-moving neutrons its nucleus splits into two substantial fragments plus several neutrons and 3 1011 J of kinetic energy. The fast moving fragments hit surrounding atoms producing heat before coming to rest. The neutrons travel further, hitting atoms and producing further fissions. Hence the number of neutrons increases, causing, under the correct conditions, a chain reaction. In conventional reactors the core or moderator slows down the moving neutrons to achieve more effective splitting of the nuclei.
Fuels used in reactors have some component of 235U. Natural uranium is sometimes used although the energy density is considerably less than for enriched uranium. The basic reactor consists of the fuel in the form of rods or pellets situated in
an environment (moderator) which will slow down the neutrons and fission products and in which the heat is evolved. The moderator can be light or heavy water or
graphite. Also situated in the moderator are movable rods which absorb neutrons
and hence exert control over the fission process. In some reactors the cooling fluid is
pumped through channels to absorb the heat, which is then transferred to a secondary loop in which steam is produced for the turbine. In water reactors the moderator
itself forms the heat-exchange fluid.
A number of versions of the reactor have been used with different coolants
and types of fissile fuel. In Britain the first generation of nuclear power stations
used Magnox reactors in which natural uranium in the form of metal rods was
enclosed in magnesium-alloy cans. The fuel cans were placed in a structure or
core of pure graphite made up of bricks (called the moderator). This graphite core
slowed down the neutrons to the correct range of velocities in order to provide the
maximum number of collisions. The fission process was controlled by the insertion
of control rods made of neutron-absorbing material; the number and position of
these rods controlled the heat output of the reactor. Heat was removed from the
graphite via carbon dioxide gas pumped through vertical ducts in the core. This
heat was then transferred to water to form steam via a heat exchanger. Once the
steam had passed through the high-pressure turbine it was returned to the heat
exchanger for reheating, as in a coal- or oil-fired boiler.
A reactor similar to the Magnox is the advanced gas-cooled reactor (AGR) which
is still in use in Britain but now coming towards the end of its service life. A
reinforced-concrete, steel-lined pressure vessel contains the reactor and heat
exchanger. Enriched uranium dioxide fuel in pellet form, encased in stainless steel
cans, is used; a number of cans are fitted into steel fitments within a graphite tube to form a cylindrical fuel element which is placed in a vertical channel in the core.
Depending on reactor station up to eight fuel elements are held in place one above
the other by a tie bar. Carbon dioxide gas, at a higher pressure than in the Magnox
type, removes the heat. The control rods are made of boron steel. Spent fuel elements when removed from the core are stored in a special chamber and lowered
into a pond of water where they remain until the level of radioactivity has decreased
sufficiently for them to be removed from the station and disassembled.
In the USA and many other countries pressurized-water and boiling-water
reactors are used. In the pressurized-water type the water is pumped through the
reactor and acts as a coolant and moderator, the water being heated to 315 C at
around 150 bar pressure. At this temperature and pressure the water leaves the
reactor at below boiling point to a heat exchanger where a second hydraulic circuit
feeds steam to the turbine. The fuel is in the form of pellets of uranium dioxide in
bundles of zirconium alloy.
The boiling-water reactor was developed later than the pressurized-water
type. Inside the reactor, heat is transferred to boiling water at a pressure of 75 bar
(1100 p.s.i.). Schematic diagrams of these reactors are shown in Figures 1.7 and 1.8.
The ratio of pressurized-water reactors to boiling-water reactors throughout the
world is around 60/40%.
Both pressurized- and boiling-water reactors use light water.1 The practical
pressure limit for the pressurized-water reactor is about 160 bar (2300 p.s.i.), which
limits its efficiency to about 30%. However, the design is relatively straightforward
and experience has shown this type of reactor to be stable and dependable. In the
boiling-water reactor the efficiency of heat removal is improved by use of the
latent heat of evaporation. The steam produced flows directly to the turbine, causing possible problems of radioactivity in the turbine. The fuel for both light-water
reactors is uranium enriched to 3–4% 235U. Boiling-water reactors are probably the
cheapest to construct; however, they have a more complicated fuel make up with
different enrichment levels within each pin. The steam produced is saturated and
requires wet-steam turbines. A further type of water reactor is the heavy-water CANDU type developed by Canada. Its operation and construction are similar to
the light-water variety but this design uses naturally occurring, un-enriched or
slightly enriched uranium.
Concerns over the availability of future supplies of uranium led to the construction of a number of prototype breeder reactors. In addition to heat, these reactors
produce significant new fissile material. However, their cost, together with the technical and environmental challenges of breeder reactors, led to most of these programmes being abandoned and it is now generally considered that supplies of
uranium are adequate for the foreseeable future.
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