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A cutaway view of the BORAX-V facility. BORAX III steam turbine and generator. The BORAX Experiments were a series of safety experiments on boiling water nuclear reactors conducted by Argonne National Laboratory in the 1950s and 1960s at the National Reactor Testing Station in eastern Idaho. [1]
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.
A boiling water reactor uses demineralized water as a coolant and neutron moderator. Heat is produced by nuclear fission in the reactor core, and this causes the cooling water to boil, producing steam. The steam is directly used to drive a turbine, after which it is cooled in a condenser and converted back to liquid water. This water is then ...
The final safety evaluation report accepted by the NRC reports an overall core damage frequency of 1.65 * 10 −8 per year (i.e., roughly once every 60 million years). [ 3 ] Similarly to the ABWR, The containment is inerted with nitrogen before operation to prevent fires, and can be deinerted after reactor shutdown for maintenance.
The SCWR operates at supercritical pressure. The reactor outlet coolant is supercritical water.Light water is used as a neutron moderator and coolant. Above the critical point, steam and liquid become the same density and are indistinguishable, eliminating the need for pressurizers and steam generators (), or jet/recirculation pumps, steam separators and dryers ().
Supercritical water exists at temperatures above 374 °C and pressures above 220 atmospheres. Diagram of a supercritical water-cooled nuclear reactor. A supercritical steam generator is a type of boiler that operates at supercritical pressure and temperature, frequently used in the production of electric power.
This Wikipedia page provides a comprehensive list of boiling and freezing points for various solvents.
The progenitor of the BWR line was the 5 MW Vallecitos Boiling Water Reactor (VBWR), brought online in October 1957. Six design iterations, BWR-1 through BWR-6, were introduced between 1955 and 1972. This was followed by the Advanced Boiling Water Reactor (ABWR) introduced in the 1990s and the Economic Simplified Boiling Water Reactor (ESBWR ...