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  2. Nuclear reactor safety system - Wikipedia

    en.wikipedia.org/wiki/Nuclear_reactor_safety_system

    An LPCI is an emergency system which consists of a pump that injects a coolant into the reactor vessel once it has been depressurized. In some nuclear power plants an LPCI is a mode of operation of a residual heat removal system, also known as an RHR or RHS but is generally called LPCI. It is also not a stand-alone valve or system.

  3. Boiling water reactor safety systems - Wikipedia

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

    The Reactor Protection System (RPS) is a system, computerized in later BWR models, that is designed to automatically, rapidly, and completely shut down and make safe the Nuclear Steam Supply System (NSSS – the reactor pressure vessel, pumps, and water/steam piping within the containment) if some event occurs that could result in the reactor entering an unsafe operating condition.

  4. Boiling water reactor - Wikipedia

    en.wikipedia.org/wiki/Boiling_water_reactor

    Another example was the Isolation Condenser system, which relied on the principle of hot water/steam rising to bring hot coolant into large heat exchangers located above the reactor in very deep tanks of water, thus accomplishing residual heat removal. Yet another example was the omission of recirculation pumps within the core; these pumps were ...

  5. 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.

  6. 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 ...

  7. Advanced heavy-water reactor - Wikipedia

    en.wikipedia.org/wiki/Advanced_heavy-water_reactor

    Fuel is occupied by 452 lattice locations and the remaining 37 locations are occupied by shutdown system-1. This consists of 37 shut-off rods, 24 locations are for reactive control devices which are consisted of 8 absorber rods, 8 shim rods, and 8 regulating rods. By boiling light water at a pressure of 7 MPa, heat is then removed. The main ...

  8. Fukushima nuclear accident (Unit 3 Reactor) - Wikipedia

    en.wikipedia.org/wiki/Fukushima_nuclear_accident...

    Following the reactor SCRAM, operators activated the reactor core isolation cooling system (RCIC) and the residual heat removal system and core spray systems were made available to cool the suppression pool; whether they were activated prior to the tsunami has not been made clear. The RHRS and CS pumps were knocked out of commission by the tsunami.

  9. Loss-of-pressure-control accident - Wikipedia

    en.wikipedia.org/wiki/Loss-of-pressure-control...

    When pressure control is lost in a reactor plant, depending on the level of heat being generated by the reactor plant, the heat being removed by the steam or other auxiliary systems, the initial pressure, and the normal operating temperature of the plant, it could take minutes or even hours for operators to see significant trends in core behaviour.