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A reactor protection system is designed to immediately terminate the nuclear reaction. By breaking the nuclear chain reaction, the source of heat is eliminated.Other systems can then be used to remove decay heat from the core.
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.
Print/export Download as PDF; Printable version; ... Pages in category "Nuclear reactor safety" The following 13 pages are in this category, out of 13 total.
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 ...
In the context of nuclear reactors, a safety code is a computer program used to analyze the safety of a reactor, or to simulate possible accident conditions. This article appears to be a dictionary definition .
This risk analysis allows decision making of any changes within a nuclear power plant in accordance with legislation, safety margins, and performance strategies. A 2003 study commissioned by the European Commission remarked that "core damage frequencies of 5 × 10 −5 [per reactor-year] are a common result" or in other words, one core damage ...
An important concern in the nuclear safety field is the aging of nuclear reactors. Quality Assurance Technicians, weld inspectors and radiographers use ultrasonic waves to look for cracks and other defects in hot metal parts, in order to identify "microscale" defects that lead to big cracks. [14]
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).