According to GEH, the ESBWR is the world’s safest approved nuclear reactor design based on core damage frequency. The reactor has. generation nuclear reactor, commonly referred to as the “ESBWR”. No other use, direct or indirect, of the document or the information it contains is authorized;. The COL references GE Hitachi Nuclear Energy’s (GEH) Economic Simplified Boiling Water Reactor (ESBWR), which received design.
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The passive safety systems in an ESBWR operate without using any pumps, which creates increased design safety, integrity, and reliability, while simultaneously reducing overall reactor cost. It also uses natural circulation to esbwrr coolant flow within the reactor pressure vessel RPV ; this results in fewer systems to maintain, and precludes significant BWR casualties such as recirculation line breaks.
Economic Simplified Boiling Water Reactor – Wikipedia
There are no circulation pumps or associated piping, power supplies, heat exchangers, instrumentation, or controls needed for these systems. These systems utilize natural circulation based on simple laws of physics to transfer the decay heat outside containment while maintaining water levels inside the reactor, keeping the nuclear fuel submerged in water and adequately cooled.
In events where the reactor coolant pressure boundary remains intact, the Isolation Condenser System ICS is used to remove decay heat from the reactor and transfer it outside containment. The ICS system is a closed loop system that connects the reactor pressure vessel to a heat exchanger located in the upper elevation of the reactor building.
Steam leaves the reactor through the ICS piping and travels to the ICS heat exchangers which are submerged in a large pool. The steam is condensed in the heat exchangers and the denser condensate then flows back down to the reactor to complete the cooling loop. Reactor coolant is cycled through this flow path to provide continuous cooling and to add water to the reactor core.
In cases where the reactor coolant pressure boundary does not remain intact and water inventory in the core is being lost, the Passive Containment Cooling System PCCS and Gravity Driven Cooling System GDCS work in concert to maintain the water level in the core and remove decay heat from the reactor by transferring it outside containment.
If the water level inside the reactor pressure vessel drops to a predetermined level, due to the loss of water inventory, the reactor is depressurized and the GDCS is initiated. It consists of large pools of water inside containment located above the reactor that are connected to the reactor pressure vessel. When the GDCS system is initiated, gravity forces water to flow from the pools into the reactor. The pools are sized to provide sufficient amounts of water to maintain the water at a level above the top of the nuclear fuel.
After the reactor has been depressurized, the decay heat is transferred to the containment as water inside the reactor boils and exits the reactor pressure vessel into the containment in the form of steam. The Reacyor consists of a set of heat exchangers located in the upper wsbwr of the reactor building.
The steam from the reactor reactot through the containment to the PCCS heat exchangers where the steam is condensed. The condensate then drains from the PCCS heat exchangers back to the GDCS pools where it completes the cycle and drains back to the reactor pressure vessel.
Both the ICS and PCCS heat exchangers are submerged in a pool of water large enough to provide 72 hours of reactor decay heat removal capability. The pool is vented to the atmosphere and is located outside of the containment. The combination of these features allows the pool to be refilled easily with low pressure water sources and installed piping.
The reactor core is shorter than in conventional Edbwr plants to reduce the pressure drop over the fuel, thereby enabling natural circulation. In case of an accident, the ESBWR can remain in a safe, stable state for 72 hours without any operator action or even electrical power.
ESBWR safety systems are designed to operate normally in the event of station blackout, which prevented proper functioning of the emergency core geactor systems at ebwr Fukushima Daiichi Nuclear Power Plant.
Below the vessel, there is a piping structure that allows for cooling of the core during any very rezctor accident. These pipes facilitate cooling above and below the molten core with water.
The final safety evaluation report accepted by the NRC reports an overall core damage frequency of 1. On June 7,the NRC completed its public comment period. The NRC granted approval in September From Wikipedia, the free encyclopedia.
First licence for ESBWR
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