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  2. Zirconium alloys - Wikipedia

    en.wikipedia.org/wiki/Zirconium_alloys

    Zirconium cladding rapidly reacts with water steam above 1,500 K (1,230 °C). [15] [16] Oxidation of zirconium by water is accompanied by release of hydrogen gas. This oxidation is accelerated at high temperatures, e.g. inside a reactor core if the fuel assemblies are no longer completely covered by liquid water and insufficiently cooled. [17]

  3. Fuel element failure - Wikipedia

    en.wikipedia.org/wiki/Fuel_element_failure

    A fuel element failure is a rupture in a nuclear reactor's fuel cladding that allows the nuclear fuel or fission products, either in the form of dissolved radioisotopes or hot particles, to enter the reactor coolant or storage water. [1] The de facto standard nuclear fuel is uranium dioxide or a mixed uranium/plutonium dioxide.

  4. Nuclear reactor safety system - Wikipedia

    en.wikipedia.org/wiki/Nuclear_reactor_safety_system

    The fuel cladding is the first layer of protection around the nuclear fuel and is designed to protect the fuel from corrosion that would spread fuel material throughout the reactor coolant circuit. In most reactors it takes the form of a sealed metallic or ceramic layer.

  5. Spent fuel pool - Wikipedia

    en.wikipedia.org/wiki/Spent_fuel_pool

    Example of a spent fuel pool from the shut-down Caorso Nuclear Power Plant. This pool is not holding large amounts of material. Spent fuel pools (SFP) are storage pools (or "ponds" in the United Kingdom) for spent fuel from nuclear reactors. They are typically 40 or more feet (12 m) deep, with the bottom 14 feet (4.3 m) equipped with storage ...

  6. Boiling water reactor safety systems - Wikipedia

    en.wikipedia.org/wiki/Boiling_water_reactor...

    The five criteria for ECCS are to prevent peak fuel cladding temperature from exceeding 2200 °F (1204 °C), prevent more than 17% oxidation of the fuel cladding, prevent more than 1% of the maximum theoretical hydrogen generation due the zircalloy metal-water reaction, maintain a coolable geometry, and allow for long-term cooling.

  7. Behavior of nuclear fuel during a reactor accident - Wikipedia

    en.wikipedia.org/wiki/Behavior_of_nuclear_fuel...

    The temperature of the pipe was monitored by thermocouples and for the tests conducted under PWR conditions the water entering the larger pipe (14.2 mm diameter) holding the test metal pipe (9.5 mm outside diameter and 600 mm long) was at 280 °C and 15 MPa.

  8. Loss-of-coolant accident - Wikipedia

    en.wikipedia.org/wiki/Loss-of-coolant_accident

    The Fukushima Daiichi nuclear disaster in 2011 occurred due to a loss-of-coolant accident. The circuits that provided electrical power to the coolant pumps failed causing a loss-of-core-cooling that was critical for the removal of residual decay heat which is produced even after active reactors are shut down and nuclear fission has ceased.

  9. Passive nuclear safety - Wikipedia

    en.wikipedia.org/wiki/Passive_nuclear_safety

    Passive nuclear safety is a design approach for safety features, implemented in a nuclear reactor, that does not require any active intervention on the part of the operator or electrical/electronic feedback in order to bring the reactor to a safe shutdown state, in the event of a particular type of emergency (usually overheating resulting from a loss of coolant or loss of coolant flow).