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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.
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] They were performed using the five BORAX reactors that were designed and built by Argonne. [2]
The first generation of production boiling water reactors saw the incremental development of the unique and distinctive features of the BWR: the torus (used to quench steam in the event of a transient requiring the quenching of steam), as well as the drywell, the elimination of the heat exchanger, the steam dryer, the distinctive general layout ...
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.
Download as PDF; Printable version; In other projects Wikimedia Commons; ... Boiling water reactor safety systems; E. Economic Simplified Boiling Water Reactor; G. GE BWR
The Economic Simplified Boiling Water Reactor (ESBWR) is a passively safe generation III+ reactor design derived from its predecessor, the Simplified Boiling Water Reactor (SBWR) and from the Advanced Boiling Water Reactor (ABWR). All are designs by GE Hitachi Nuclear Energy (GEH), and are based on previous Boiling Water Reactor designs.
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 ...
This caused the initiation of safety injection systems, and for the next 30 minutes reactor water level and pressure seesawed as the operators attempted to stabilize the reactor. It was not until two hours later that reactor level, reactor pressure and drywell pressure were reduced to normal. [ 5 ]