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A nuclear reactor generates heat in the fuel rod and transfers it to the coolant. Research the
design of the fuel rod and the heat transfer process. Describe the process including heat transfer
coefficients. Describe differences in efficiencies between BWR and PWR processes.
Solution
>>
A nuclear reactor produces and controls the release of energy from splitting the atoms of certain
elements. In a nuclear power reactor, the energy released is used as heat to make steam to
generate electricity. (In a research reactor the main purpose is to utilise the actual neutrons
produced in the core. In most naval reactors, steam drives a turbine directly for propulsion.)
The principles for using nuclear power to produce electricity are the same for most types of
reactor. The energy released from continuous fission of the atoms of the fuel is harnessed as heat
in either a gas or water, and is used to produce steam. The steam is used to drive the turbines
which produce electricity (as in most fossil fuel plants).
The world's first nuclear reactors operated naturally in a uranium deposit about two billion years
ago. These were in rich uranium orebodies and moderated by percolating rainwater. The 17
known at Oklo in west Africa, each less than 100 kW thermal, together consumed about six
tonnes of that uranium. It is assumed that these were not unique worldwide.
Today, reactors derived from designs originally developed for propelling submarines and large
naval ships generate about 85% of the world's nuclear electricity. The main design is the
pressurised water reactor (PWR) which has water at over 300°C under pressure in its primary
cooling/heat transfer circuit, and generates steam in a secondary circuit. The less numerous
boiling water reactor (BWR) makes steam in the primary circuit above the reactor core, at similar
temperatures and pressure. Both types use water as both coolant and moderator, to slow
neutrons. Since water normally boils at 100°C, they have robust steel pressure vessels or tubes to
enable the higher operating temperature. (Another type uses heavy water, with deuterium atoms,
as moderator. Hence the term ‘light water’ is used to differentiate.)
>> Pressurized Water Heater (PWR)
A PWR has fuel assemblies of 200-300 rods each, arranged vertically in the core, and a large
reactor would have about 150-250 fuel assemblies with 80-100 tonnes of uranium.
Water in the reactor core reaches about 325°C, hence it must be kept under about 150 times
atmospheric pressure to prevent it boiling. Pressure is maintained by steam in a pressuriser (see
diagram). In the primary cooling circuit the water is also the moderator, and if any of it turned to
steam the fission reaction would slow down. This negative feedback effect is one of the safety
features of the type. The secondary shutdown system involves adding boron to the primary
circuit.
The secondary circuit is under less pressure and the water here boils in the heat exchangers
which are thus steam generators. The steam drives the turbine to produce electricity, and is then
condensed and returned to the heat exchangers in contact with the primary circuit.
>> Boiling Water Heater (BWR)
This design has many similarities to the PWR, except that there is only a single circuit in which
the water is at lower pressure (about 75 times atmospheric pressure) so that it boils in the core at
about 285°C. The reactor is designed to operate with 12-15% of the water in the top part of the
core as steam, and hence with less moderating effect and thus efficiency there. BWR units can
operate in load-following mode more readily then PWRs.
The steam passes through drier plates (steam separators) above the core and then directly to the
turbines, which are thus part of the reactor circuit. Since the water around the core of a reactor is
always contaminated with traces of radionuclides, it means that the turbine must be shielded and
radiological protection provided during maintenance. The cost of this tends to balance the
savings due to the simpler design. Most of the radioactivity in the water is very short-lived*, so
the turbine hall can be entered soon after the reactor is shut down.
* mostly N-16, with a 7 second half-life
A BWR fuel assembly comprises 90-100 fuel rods, and there are up to 750 assemblies in a
reactor core, holding up to 140 tonnes of uranium. The secondary control system involves
restricting water flow through the core so that more steam in the top part reduces moderation.

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Discus this topic..A nuclear reactor generates heat in the fuel ro.pdf

  • 1. Discus this topic.. A nuclear reactor generates heat in the fuel rod and transfers it to the coolant. Research the design of the fuel rod and the heat transfer process. Describe the process including heat transfer coefficients. Describe differences in efficiencies between BWR and PWR processes. Solution >> A nuclear reactor produces and controls the release of energy from splitting the atoms of certain elements. In a nuclear power reactor, the energy released is used as heat to make steam to generate electricity. (In a research reactor the main purpose is to utilise the actual neutrons produced in the core. In most naval reactors, steam drives a turbine directly for propulsion.) The principles for using nuclear power to produce electricity are the same for most types of reactor. The energy released from continuous fission of the atoms of the fuel is harnessed as heat in either a gas or water, and is used to produce steam. The steam is used to drive the turbines which produce electricity (as in most fossil fuel plants). The world's first nuclear reactors operated naturally in a uranium deposit about two billion years ago. These were in rich uranium orebodies and moderated by percolating rainwater. The 17 known at Oklo in west Africa, each less than 100 kW thermal, together consumed about six tonnes of that uranium. It is assumed that these were not unique worldwide. Today, reactors derived from designs originally developed for propelling submarines and large naval ships generate about 85% of the world's nuclear electricity. The main design is the pressurised water reactor (PWR) which has water at over 300°C under pressure in its primary cooling/heat transfer circuit, and generates steam in a secondary circuit. The less numerous boiling water reactor (BWR) makes steam in the primary circuit above the reactor core, at similar temperatures and pressure. Both types use water as both coolant and moderator, to slow neutrons. Since water normally boils at 100°C, they have robust steel pressure vessels or tubes to enable the higher operating temperature. (Another type uses heavy water, with deuterium atoms, as moderator. Hence the term ‘light water’ is used to differentiate.) >> Pressurized Water Heater (PWR) A PWR has fuel assemblies of 200-300 rods each, arranged vertically in the core, and a large reactor would have about 150-250 fuel assemblies with 80-100 tonnes of uranium. Water in the reactor core reaches about 325°C, hence it must be kept under about 150 times atmospheric pressure to prevent it boiling. Pressure is maintained by steam in a pressuriser (see diagram). In the primary cooling circuit the water is also the moderator, and if any of it turned to
  • 2. steam the fission reaction would slow down. This negative feedback effect is one of the safety features of the type. The secondary shutdown system involves adding boron to the primary circuit. The secondary circuit is under less pressure and the water here boils in the heat exchangers which are thus steam generators. The steam drives the turbine to produce electricity, and is then condensed and returned to the heat exchangers in contact with the primary circuit. >> Boiling Water Heater (BWR) This design has many similarities to the PWR, except that there is only a single circuit in which the water is at lower pressure (about 75 times atmospheric pressure) so that it boils in the core at about 285°C. The reactor is designed to operate with 12-15% of the water in the top part of the core as steam, and hence with less moderating effect and thus efficiency there. BWR units can operate in load-following mode more readily then PWRs. The steam passes through drier plates (steam separators) above the core and then directly to the turbines, which are thus part of the reactor circuit. Since the water around the core of a reactor is always contaminated with traces of radionuclides, it means that the turbine must be shielded and radiological protection provided during maintenance. The cost of this tends to balance the savings due to the simpler design. Most of the radioactivity in the water is very short-lived*, so the turbine hall can be entered soon after the reactor is shut down. * mostly N-16, with a 7 second half-life A BWR fuel assembly comprises 90-100 fuel rods, and there are up to 750 assemblies in a reactor core, holding up to 140 tonnes of uranium. The secondary control system involves restricting water flow through the core so that more steam in the top part reduces moderation.