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The Automatic depressurization system is not a part of the cooling system proper, but is an essential adjunct to the ECCS. It is designed to activate in the event that there is either a loss of high-pressure cooling to the vessel or if the high-pressure cooling systems cannot maintain the RPV water level.
GE Energy ESBWR website; Status report 100 - Economic Simplified Boiling Water Reactor (ESBWR) [permanent dead link ], ARIS, IAEA, 01-08-2011; POWER magazine article on the ESBWR Archived 2011-10-02 at the Wayback Machine; NRC ESBWR Overview page; ESBWR Probabilistic Risk Assessment; ESBWR Design Control Document, Rev. 10
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 ...
BWR designs operate constantly at about half the primary system pressure of PWR designs while producing the same quantity and quality of steam in a compact system: 1020 psi (7 MPa) reactor vessel pressure, and 288 °C temperature for BWR which is lower than 2240 psi (14.4 MPa) and 326 °C for PWR.
Eighteen SORVs (safety overpressure relief valves), eight of which are part of the ADS (automatic depressurization system), ensure that RPV overpressure events are quickly mitigated, and that if necessary, that the reactor can be depressurized rapidly to a level where low pressure core flooder (LPCF, the high-capacity mode of the residual heat ...
Broths are rich with amino acids, minerals, and inflammatory properties that may stimulate the immune system, helping to clear out your congestion. Eat certain foods.
These are glaring examples of a civil justice system that is not working for all Louisianas. In fact, it is costing taxpayers and businesses every single day, extracting an annual "tort tax" of ...
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).