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| Nuclear
reactor and primary coolant system |
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Primary Coolant System
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1.
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Reactor Pressure Vessel
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2.
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Steam Generator
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3.
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Primary Coolant Pump
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4.
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Pressuriser
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The fuel assemblies which form the reactor core, are loaded
into a specially fabricated cylindrical steel pressure vessel
(the reactor pressure vessel). The reactor pressure vessel
is about 12 metres high and has a 20 cm thick steel wall
with an inner diameter of about 4 metres. It weighs about
314 tonnes. The primary coolant system of a 900 MW class
reactor consists of the reactor pressure vessel and the
primary circuit with 3 identical loop (Top figure). Each
loop has a primary coolant pump, a steam generator and the
interconnected piping. A pressuriser is installed in one
of the 3 loops. Each primary coolant pump will circulate
the cooling water (ordinary water) around the loop through
the reactor core at a high pressure of about 155 bar (1
bar = 100 kPa). In addition to its moderator
function, the cooling water would also transfer the heat
from the reactor core to the steam generator. The water
temperature at the reactor pressure vessel outlet is about
330 degree C whereas the water temperature at the inlet
of the vessel is about 290 degree C. The cooling water is
in a sub-cooled condition at such high temperature and pressure
to prevent it from boiling. The steam generator of about
20 metres in height is fitted with U tubes in the inside
which serve as the heat exchanger to transfer the heat from
the water in primary circuit to that in the secondary circuit.
The heat will convert the feed water in the secondary circuit
to steam for driving the turbine-generator (Right figure).
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Primary Coolant Circuit
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The pressuriser is mainly used to maintain the pressure in
the primary coolant circuit and prevent overpressure. It is a cylindrical pressure vessel of about 2
m in diameter and about 13 m long, tapping off from
one of the hot legs in the primary loops. The steam and
water volumes occupy the top half and bottom half
of the pressuriser respectively during normal operation.
There are water spray nozzles at the top and a group of
heaters at the bottom of the pressuriser. The water level
inside the pressuriser and thus the pressure in the primary coolant
circuit can be controlled by operation of the heaters and
water spray. A sophisticated pressuriser level control system
is used to regulate the water level inside the pressuriser
so as to ensure a proper pressure control during reactor
power change and transient plant operation. The heaters
will be turned on to increase steam production if the pressure
drops. If the pressure increases, the water spray will be
turned on to condense the steam to reduce the pressure.
In addition, the control system will provide a protection
signal to shutdown the reactor automatically if the pressure
inside the pressuriser is too high or too low.
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| At the first start up of a new reactor, primary source
rods consisted of californium-252 are inserted into the
reactor
to produce sufficient neutrons to initiate the first fission.
Secondary source rods consisted of antimony and beryllium
are also inserted at the same time to provide a regenerative
neutron source such that it will initiate nuclear
fission
in subsequent start up of the reactor throughout its service
life. To ensure nuclear
safety and allow control of the fission rate inside
the reactor, some fuel assemblies are fitted with control
rods.
Each control rod assembly consists of a number of absorber
rods attached to a spider assembly and coupled to the
control
rod drive mechanism. The absorber rods are made up of neutron
absorbers such as silver, indium and cadmium. Hence, by
adjusting the
position of the control rods, the number of neutrons and
thus the fission rate in the reactor can be controlled.
The control rod assemblies
are fitted with driving mechanism to move the control rods
up and down in the reactor core for controlling the start
up of the reactor, adjusting its power output, and enable
the normal shutdown of the reactor and scram.
In addition, the fission rate in the PWR can also be
controlled
by adjusting the boron (a neutron absorber) concentration
in the primary coolant circuit. After start up of the
reactor and
attaining its desired power output, it would be maintained
at criticality
for stable operation at power. The reactor can be shutdown
during emergency by cutting off the power supply to the
control
rod driving mechanism which then causes the control rods
to drop down to the reactor core by gravity quickly and
thereby
stopping the nuclear fission immediately.
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The above information
is provided by EMSD
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