In the BWR each fuel assembly is encased in a thin walled tube, which is presumably what you are referring to. It is not a fixed part of the reactor structure. This is introduced because in the BWR steam is produced in the coolant, unlike in the PWR which is at a higher pressure to suppress boiling. The voids produced by the steam bubbles introduce a type of reactor response which does not occur in PWR's, namely that if power in a fuel assembly increases, more voids are created which has a negative effect on the reactor's criticality and so this has a self stabilising characteristic, which is beneficial. However it is found to give more reactor stability if each fuel assembly is separated from its neighbours.
Nuclear fission takes place in the nuclear fuel rods that are placed in the reactor core that is situated in the reactor pressure vessel. The reactor pressure vessel is usually situated inside the reactor containment.
In the PWR and BWR types it is a matrix of fuel assemblies stabilised with zircaloy fittings, and with control rods in certain specified channels within this matrix. This is where the nuclear heat is generated, and this heat is carried away by a flow of very pure water circulated by large pumps and at a high pressure.
for pressurized light water reactor type, as an example, the nuclear reactor components are * Reactor vessel (that contains the nuclear fuel and surrounded with water and contains control rod for power control and for safety) * reactor coolant pump * steam generator * reactor pressurizer * piping out of the vessel to the pressurizer, from pressurizer to steam generator, from steam generator to reactor coolant pump, and from pump back to the reactor vessel.
CANDU, a reactor type designed in Canada which uses heavy water as the primary coolant.
The nuclear fuel is found in the fuel rods. These fuel rods are formed into fuel bundles called fuel assemblies, and together they make up the reactor core.
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Nuclear fission takes place in the nuclear fuel rods that are placed in the reactor core that is situated in the reactor pressure vessel. The reactor pressure vessel is usually situated inside the reactor containment.
In the PWR and BWR types it is a matrix of fuel assemblies stabilised with zircaloy fittings, and with control rods in certain specified channels within this matrix. This is where the nuclear heat is generated, and this heat is carried away by a flow of very pure water circulated by large pumps and at a high pressure.
A reactor using light water as moderator and coolant. The primary circuit including the reactor inside its pressure vessel is kept at a high enough pressure to suppress boiling, and the reactor coolant water is circulated through external steam raising units, where heat is transferred to secondary water at a lower pressure so that steam is produced, which then feeds a conventional steam turbine/generator. The uranium fuel is enriched in U-235 to 4-5 percent, and is in the form of uranium dioxide, made up into fuel rods 10mm in diameter and encased in zircaloy sheaths. A number of rods is made into an assembly which is the unit loaded and unloaded during refuelling outages. About 1/3 of the assemblies are changed in each fuelling outage, when the head of the pressure vessel is removed for access. You can read more and see a diagram in the link given below
A reactor using light water as moderator and coolant. The primary circuit including the reactor inside its pressure vessel is kept at a high enough pressure to suppress boiling, and the reactor coolant water is circulated through external steam raising units, where heat is transferred to secondary water at a lower pressure so that steam is produced, which then feeds a conventional steam turbine/generator. The uranium fuel is enriched in U-235 to 4-5 percent, and is in the form of uranium dioxide, made up into fuel rods 10mm in diameter and encased in zircaloy sheaths. A number of rods is made into an assembly which is the unit loaded and unloaded during refuelling outages. About 1/3 of the assemblies are changed in each fuelling outage, when the head of the pressure vessel is removed for access. You can read more and see a diagram in the link given below
The pressure vessel contains the reactor core with its fuel, coolant, moderator, control elements, and emergency systems. The turbine is the device that on receiving the steam it spins and turns the electric generators to produce electricity.
For the PWR, the reactor core which is an array of fuel assemblies, inside a very strong pressure vessel made of thick steel. The top of the vessel is removable for fuelling, and also holds the control rods and their mechanisms. The whole thing is enclosed in a secondary containment. Also inside this is the primary circuit which circulates water through the core to carry away the heat produced by the fuel assemblies, and the secondary circuit steam raising units which send steam to the turbine. See link below
yes
Heat is eliminated through use of reactor coolant passing over the nuclear fuel in the primary coolant loops.
For a PWR, how about: Pressure Vessel, Closure Head Assembly, Core Support, Inlet/Outlet Nozzles, Fuel assemblies, Control Rods and Drive Mechanisms
for pressurized light water reactor type, as an example, the nuclear reactor components are * Reactor vessel (that contains the nuclear fuel and surrounded with water and contains control rod for power control and for safety) * reactor coolant pump * steam generator * reactor pressurizer * piping out of the vessel to the pressurizer, from pressurizer to steam generator, from steam generator to reactor coolant pump, and from pump back to the reactor vessel.
The central active core fuel assemblies.