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Schematic GE BWR inside a Mark I containment. General Electric's BWR product line of boiling water reactors represents the designs of a relatively large (~18%) [1] percentage of the commercial fission reactors around the world. The progenitor of the BWR line was the 5 MW Vallecitos Boiling Water Reactor (VBWR), brought online in October 1957.
Positioning (withdrawing or inserting) control rods is the normal method for controlling power when starting up a BWR. As control rods are withdrawn, neutron absorption decreases in the control material and increases in the fuel, so reactor power increases.
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 BWR at GE's Vallecitos Nuclear Center and the AEC's BORAX experiments provided research data and operator training for Dresden. The core contained 488 fuel subassemblies, 80 control rods, and 8 instrument nozzles. Each subassembly contained 36 fuel rods in a Zircaloy-2 channel. The fuel was uranium dioxide clad in Zircaloy-2 tube. The core ...
Control rods are used in nuclear reactors to control the rate of fission of the nuclear fuel – uranium or plutonium. Their compositions include chemical elements such as boron , cadmium , silver , hafnium , or indium , that are capable of absorbing many neutrons without themselves decaying.
Control rods are a series of rods that can be quickly inserted into the reactor core to absorb neutrons and rapidly terminate the nuclear reaction. [2] They are typically composed of actinides, lanthanides, transition metals, and boron, [3] in various alloys with structural backing such as steel. In addition to being neutron absorbent, the ...
Columbia Generating Station is a BWR-5. It features a Mark II containment structure. The reactor core holds up to 764 fuel assemblies, and 185 control rods, more technically known as control blades. The reactor is licensed for a power output of 3486 thermal megawatts (MWt). The gross electrical output of the plant is 1230 megawatts-electric (MWe).
Slightly different versions of the ABWR are offered by GE-Hitachi, Hitachi-GE, and Toshiba. [5]In 1997 the GE-Hitachi U.S. ABWR design was certified as a final design in final form by the U.S. Nuclear Regulatory Commission, meaning that its performance, efficiency, output, and safety have already been verified, making it bureaucratically easier to build it rather than a non-certified design.