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The Mitsubishi advanced pressurized water reactor (APWR) is a generation III nuclear reactor design developed by Mitsubishi Heavy Industries (MHI) based on pressurized water reactor technology. It features several design enhancements including a neutron reflector, improved efficiency and improved safety systems. It has safety features advanced ...
The example of components are pump compressor, turbine, reactor, and heat exchanger. By considering the constitutive equation for the given type of fluid, thermodynamic state of each point can be analyzed. As a result, the thermal efficiency of the cycle can be defined. Examples of the cycle include the Carnot cycle, Brayton cycle, and Rankine ...
A pressurized water reactor (PWR) is a type of light-water nuclear reactor. PWRs constitute the large majority of the world's nuclear power plants (with notable exceptions being the UK, Japan, India and Canada).
The Reactor Water Cleanup System ensures that primary system water remains pure. Similar to the ABWR, the mPower reactor had integral coolant recirculation pumps inside the Integral Reactor Vessel (IRV). The mPower reactor control rods are inserted from the top of the core and inserted upon scram under gravity. All of the primary coolants were ...
An LPCI is an emergency system which consists of a pump that injects a coolant into the reactor vessel once it has been depressurized. In some nuclear power plants an LPCI is a mode of operation of a residual heat removal system, also known as an RHR or RHS but is generally called LPCI. It is also not a stand-alone valve or system.
The AP1000 design traces its history to two previous designs, the AP600 and the System 80.. The System 80 design was created by Combustion Engineering and featured a two-loop cooling system with a single steam generator paired with two reactor coolant pumps in each loop that makes it simpler and less expensive than systems which pair a single reactor coolant pump with a steam generator in each ...
The CAP-1400 is a Pressurized water reactor, in which the primary coolant (water) is pumped under high pressure to the reactor core where it is heated by the energy released by the fission of atoms. CAP1400 has two primary coolant loops that transfer the heat generated by the fission reaction of 235U in the reactor core to the steam generator ...
The IRIS pressure vessel and systems contained within it. The coolant system consists of a pressurizer, Steam generators, and reactor coolant pumps (RCPs).These are all located within the reactor pressure vessel, making a very small, short loop that forms the primary coolant system, see the figure on the right for the relative locations of the components.