PWR fuel assemblies
Fuel assemblies in the core of PWR Reactors
The core of a pressurized water reactor (PWR) is contained in a sealed metal vessel. It is composed of fuel rods grouped in assemblies arranged in a mosaic, between which pressurized primary water circulates evacuates heat and moderates neutrons.
A fuel assembly groups a set of rods held together by support grids. These rods are long tubes that contain stacked fuel pellets. The wall or sheath of these rods and their tips ensure the confinement of radioactive products from the high pressure and high temperature water circulating around.
The pellets are composed of sintered uranium oxides (UO2) or in the case of MOX a mixture of uranium and plutonium oxide. Uranium oxide pellets 1.35 cm high weigh 8.3 grams. A typical pressurized water PWR reactor rod contains 272 pellets from end to end. Its length is 3.85 m. Its height is 4.06 m and a weight of 500 kg. Its fuel weight is approximately 2 kg.
The advantage of the rod configuration is that the newly produced fast neutrons pass through water, which allows them to be slowed down before they reentering the fuel again to produce fissions.
In total, the core of a reactor unit which provides an electrical power of 0.90 Gigawatt includes 177 assemblies, 46,728 rods and 11,273,856 pellets. It will operate on average 6,600 hours per year. It contains 72 tonnes of heavy metal (mainly uranium) which will remain in the reactor for 3 years and will be renewed each year in thirds of 24 tonnes.
The metal sheaths, coating the fuel rods and immersed in pressurized water at high temperature, are made of zirconium, a rare metal. The use of zirconium developed from 1949 at the instigation of Admiral Rickover as part of the development of onboard reactors for the American nuclear submarines.
It was only later, through the “Atom for Peace” program, that its use was extended to the civil atom. The reasons which led to the choice of zirconium or its alloys are high transparency to neutrons, good mechanical qualities, and good resistance to water corrosion at very high temperatures. Corrosion resistance is improved through alloys, mainly based on tin, called zircaloy.
Later, when the irradiated assemblies are removed from the reactors and stored in pools, it is the sealing of these sheaths which prevents the dispersion of radioactive products and offers a first protective barrier.
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