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  2. 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.

  3. Nuclear reactor safety system - Wikipedia

    en.wikipedia.org/wiki/Nuclear_reactor_safety_system

    The Automatic Depressurization System (ADS) consists of a series of valves which open to vent steam several feet under the surface of a large pool of liquid water (known as the wetwell or torus) in pressure suppression type containments (typically used in boiling water reactor designs), or directly into the primary containment structure in ...

  4. Economic Simplified Boiling Water Reactor - Wikipedia

    en.wikipedia.org/wiki/Economic_Simplified...

    The ESBWR received a positive Safety Evaluation Report [5] and Final Design Approval [6] on March 9, 2011. On June 7, 2011, the NRC completed its public comment period. [ 7 ] Final rule was issued on September 16, 2014, after two outstanding problems with GE-Hitachi's modeling of loads on the steam dryer were solved.

  5. GE BWR - Wikipedia

    en.wikipedia.org/wiki/GE_BWR

    BWR Type 2 (BWR-2, BWR/2): Introduced in 1963, >500 MW e, typically around 650 MW e gross (Oyster Creek, Nine Mile Point 1). [ 4 ] [ 5 ] Included a large direct cycle. 5 recirculation loops, variable speed external recirculation pumps (one pump per loop, each pump's flow rate could be varied from 6,400 to 32,000 US gallons per minute (0.40 to 2 ...

  6. Advanced boiling water reactor - Wikipedia

    en.wikipedia.org/wiki/Advanced_boiling_water_reactor

    Slightly different versions of the ABWR are offered by GE-Hitachi, Hitachi-GE, and Toshiba. [5]In 1997 the GE-Hitachi U.S. ABWR design was certified as a final design in final form by the U.S. Nuclear Regulatory Commission, meaning that its performance, efficiency, output, and safety have already been verified, making it bureaucratically easier to build it rather than a non-certified design.

  7. Isolation condenser - Wikipedia

    en.wikipedia.org/wiki/Isolation_condenser

    When the IC system is activated, a valve at the bottom of the IC condenser is opened which connects to a lower area on the reactor. The water falls to the reactor via gravity, allowing the condenser to fill with steam, which then condenses. This cycle runs continuously until the bottom valve is closed. [2]

  8. 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).

  9. Process plant shutdown systems - Wikipedia

    en.wikipedia.org/wiki/Process_plant_shutdown_systems

    [2] In a typical depressurization system, the goal is typically reduce the pressure in the plant to less than 50% of the design pressure or to 7 barg, whichever is lower, within 15 minutes. [2] Disposal of blowdown fluids is generally to flare systems or, if safe to do so, non-fired blowdown drums. Blowdown may be strategically delayed by fire ...