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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.
WASH-740 was a report published by the U.S. Atomic Energy Commission (USAEC) in 1957. This report, called "Theoretical Possibilities and Consequences of Major Accidents in Large Nuclear Power Plants" (also known as "The Brookhaven Report"), estimated maximum possible damage from a meltdown with no containment building at a large nuclear reactor.
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 ...
Download as PDF; Printable version; In other projects ... In the context of nuclear reactors, a safety code is a computer program used to analyze the safety of a ...
That review must be completed before a final decision is made on the renewal. The SER and the license renewal application will be provided on a delayed schedule to the agency’s Advisory Committee on Reactor Safeguards (ACRS), an independent body of experts that advises the Commission on reactor safety matters.
Download as PDF; Printable version; In other projects Wikidata item; ... Pages in category "Nuclear reactor safety" The following 13 pages are in this category, out ...
WASH-1400, 'The Reactor Safety Study (later known as NUREG-75/014) was a report produced in 1975 for the Nuclear Regulatory Commission by a committee of specialists under Professor Norman Rasmussen. It "generated a storm of criticism in the years following its release". [ 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.