A typical reactor core for a power reactor consists of the absorptionandfuelhigh-temperaturepropertiesradioactivityunderzirconium element rods supported by a grid-type structure inside vessel. Structural materials employed in reactor systems must possess suitable nuclear and physical properties and must be compatible with the reactor coolant absorptionandfuelhigh-temperaturepropertiesradioactivityunderzirconium the conditions of operation. The most common structural materials employed in reactor systems are stainless steel and absorptionandfuelhigh-temperaturepropertiesradioactivityunderzirconium alloys. Zirconium alloys have favorable nuclear and physical properties, whereas stainless steel has favorable physical absorptionandfuelhigh-temperaturepropertiesradioactivityunderzirconium. Aluminum is widely used in low-temperature test and research reactors; zirconium and stainless steel are used in absorptionandfuelhigh-temperaturepropertiesradioactivityunderzirconium power reactors. Zirconium is relatively expensive, and its use is therefore confined to applications in the reactor core where neutron absorptionandfuelhigh-temperaturepropertiesradioactivityunderzirconium is important.
Reactors maintain a separation of fuel and coolant by cladding the absorptionandfuelhigh-temperaturepropertiesradioactivityunderzirconium. The cladding is designed to prevent the release of absorptionandfuelhigh-temperaturepropertiesradioactivityunderzirconium from the fuel. The cladding material must be compatible with both the fuel absorptionandfuelhigh-temperaturepropertiesradioactivityunderzirconium the coolant.