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Not all of the heat in a nuclear reactor is generated by the chain reaction that a scram is designed to stop. For a reactor that is scrammed after holding a constant power level for an extended period (greater than 100 hrs), about 7% of the steady-state power will remain after initial shutdown due to fission product decay that cannot be stopped.
Boiling water reactors are able to SCRAM the reactor completely with the help of their control rods. [2] In the case of a loss of coolant accident (LOCA), the water-loss of the primary cooling system can be compensated with normal water pumped into the cooling circuit.
A reactor protection system (RPS) is a set of nuclear safety and security components in a nuclear power plant designed to safely shut down the reactor and prevent the release of radioactive materials. The system can "trip" automatically (initiating a scram), or it can be tripped by the operators. Trips occur when the parameters meet or exceed ...
SCRAM bracelet, an ankle bracelet for Secure Continuous Remote Alcohol Monitoring; Salted Challenge Response Authentication Mechanism (or SCRAM), a computer security mechanism used with the Simple Authentication and Security Layer; Scram cannon, a hypothetical kinetic energy weapon based on ram accelerator technology
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 inadvertant criticality.
The Limerick Generating Station is a nuclear power plant in Pennsylvania located next to the Schuylkill River in Limerick Township, Montgomery County, northwest of Philadelphia. The facility has two General Electric boiling water reactor (BWR) units, cooled by natural draft cooling towers.
1943 Reactor diagram using boron control rods. Control rods are inserted into the core of a nuclear reactor and adjusted in order to control the rate of the nuclear chain reaction and, thereby, the thermal power output of the reactor, the rate of steam production, and the electrical power output of the power station.
On February 20, 2006, a "site area emergency" was declared at the plant at 12:28 AM. This was the first SAE declared at a US nuclear plant since 1991. Workers were shutting down Unit 1 for refueling when the plant's turbine control system malfunctioned, SCRAMing the reactor. The reactor had been operating at 6 percent power output at the time.