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This reactor was designed and is used to test nuclear fuels and materials to be used in power plants, naval propulsion, research and advanced reactors. It can operate at a maximum thermal power of 250 MW and has a "Four Leaf Clover" core design (similar to the Camunian rose ) that allows for a variety of testing locations.
The first commercial APR-1400 reactors at Shin Kori were approved in September 2007, [12] with construction starting in October 2008 (Unit 3) and August 2009 (Unit 4). [3] [13] [14] Shin Kori-3 was initially scheduled to commence operation by the end of 2013, but the schedules for both Units 3 & 4 were delayed by approximately one year to replace safety-related control cabling, which had ...
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 ...
Ōarai High-temperature engineering test reactor (HTTR) Ōarai JMTR (Japan Materials Testing Reactor) Naka JT-60 fusion reactor; Nuclear Safety Research Reactor; Fugen (ATR (Advanced Thermal Reactor), shut down) Jōyō ; Monju (FBR) Kinki University. UTR-KINKI; Kyoto University. KUR; Musashi Institute of Technology (Tokyo City University)
The second artificial nuclear reactor, the X-10 Graphite Reactor, was also a part of the Manhattan Project, as were the plutonium-producing reactors of the Hanford Engineer Works. The first nuclear bomb was code named Gadget [8] which was used in the Trinity Nuclear Test. [9] The weapon was believed to have a yield of around 20 kilotons of TNT.
Small modular reactors (SMRs) have long held the promise of cheaper, more efficient nuclear energy. Their smaller, standardized designs were expected to usher in a new era for an industry ...
Certification testing and analysis of the AP600 and AP1000 reactor designs for Westinghouse were conducted at the APEX facility at Oregon State University. The one-quarter scale reduced pressure integral system certified the passively safe systems that cool the reactor core using gravity and natural circulation.
GE further developed the BWR-1 design with the 70 MW Big Rock Point (9×9, 11×11, 12×12) reactor, which (like all GE BWR models following Dresden 1) used the more economical direct cycle method of heat transfer, but disposed with the external recirculation pumps in favor of natural circulation (an unusual strategy that only the 55 MW ...
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