The nuclear fuel of light water Pressurized Water Reactor (PWR) is fabricated as thin nuclear fuel pins assembled in an open square array of usually 17 x 17 or 18 x 18. The assembly usually keeps the central location for instrumentation and keeps also 24 locations to allow, when needed for a control rod spider to pass through in and out. This cluster of fuel pins is usually called fuel assembly.
There are about 121 to 193 fuel bundles loaded into a PWR reactor core. If you are talking about a BWR, that ranges from 368 - 800 fuel assemblies per core.
In the reactor core, which is the volume filled with the fuel assemblies
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 typical PWR has fuel assemblies of 200-300 rods each, and a large reactor would have about 150-250 such assemblies with 80-100 tonnes of uranium in all. It produces electric power in the order of 900 to 1500 MW.
PWR = pressurised water reactor. BWR = boiling water reactor
There are about 121 to 193 fuel bundles loaded into a PWR reactor core. If you are talking about a BWR, that ranges from 368 - 800 fuel assemblies per core.
For a PWR, how about: Pressure Vessel, Closure Head Assembly, Core Support, Inlet/Outlet Nozzles, Fuel assemblies, Control Rods and Drive Mechanisms
In a nuclear reactor the nuclear energy released by fission appears as heat in the fuel rods, which is then transferred to the reactor coolant (ie water in PWR and BWR)
In the reactor core, which is the volume filled with the fuel assemblies
The pressurised water reactor (PWR)
A nuclear power reactor, mainly PWR and BWR types.
The length of time we see fuel rods left in the core of a reactor will depend on the time it takes to deplete the nuclear fuel in those rods. Reactor design, specifically fuel rod design, and the rate at which the fuel is consumed during operation all have an effect. Typical life of the fuel in a nuclear reactor at a power station is several years.
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 typical PWR has fuel assemblies of 200-300 rods each, and a large reactor would have about 150-250 such assemblies with 80-100 tonnes of uranium in all. It produces electric power in the order of 900 to 1500 MW.
Yes, the pressurised water reactor (PWR)
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
Pressurised Water Reactor (PWR), Boiling Water Reactor (BWR)