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  2. Boiling water reactor safety systems - Wikipedia

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

    Examples of isolation groups include the main steamlines, the reactor water cleanup system, the reactor core isolation cooling (RCIC) system, shutdown cooling, and the residual heat removal system. For pipes which inject water into the containment, two safety-related check valves are generally used in lieu of motor operated valves.

  3. IPHWR-700 - Wikipedia

    en.wikipedia.org/wiki/IPHWR-700

    Number of fuel rods in assembly 19 elements in 3 rings 37 37 elements in 4 rings Enrichment of reload fuel 0.7% U-235 Fuel cycle length, Months 24 12 12 Average fuel burnup, MW · day / ton 6700 7500 7050 Control rods SS/Co Cadmium/SS Neutron absorber Boric Anhydride Boron Residual heat removal system Active: Shutdown cooling system

  4. 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.

  5. Nuclear reactor safety system - Wikipedia

    en.wikipedia.org/wiki/Nuclear_reactor_safety_system

    The essential service water system (ESWS) circulates the water that cools the plant's heat exchangers and other components before dissipating the heat into the environment. Because this includes cooling the systems that remove decay heat from both the primary system and the spent fuel rod cooling ponds, the ESWS is a safety-critical system. [ 7 ]

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  7. Nuclear reactor heat removal - Wikipedia

    en.wikipedia.org/wiki/Nuclear_reactor_heat_removal

    The removal of heat from nuclear reactors is an essential step in the generation of energy from nuclear reactions.In nuclear engineering there are a number of empirical or semi-empirical relations used for quantifying the process of removing heat from a nuclear reactor core so that the reactor operates in the projected temperature interval that depends on the materials used in the construction ...

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