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Example of the core of a nuclear power plant, a VVER design. A nuclear reactor core is the portion of a nuclear reactor containing the nuclear fuel components where the nuclear reactions take place and the heat is generated. [1] Typically, the fuel will be low-enriched uranium contained in thousands of individual fuel pins.
The reactor core of the APR-1400 consists of 241 fuel assemblies, 93 control element assemblies, and 61 in-core instrumentation assemblies. Each fuel assembly has 236 fuel rods in a 16 x 16 array (some space is taken up by guide tubes for control elements) containing Uranium dioxide (average enrichment of 2.6 w/o), [ 38 ] [ 37 ] [ 36 ] [ 35 ...
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 ...
TRIGA is a swimming pool reactor that can be installed without a containment building, and is designed for research and testing use by scientific institutions and universities for purposes such as undergraduate and graduate education, private commercial research, non-destructive testing and isotope production.
The core module of the ACP100 multi-purpose, small modular pressurized water reactor (PWR), also referred to as the Linglong One, is transferred to a ship on July 14, 2023, in Dalian, Liaoning ...
The blocks are stacked, surrounded by the reactor vessel into a cylindrical core with a diameter and height of 14m × 8m. [14] The maximum allowed temperature of the graphite is up to 730 °C. [15] The reactor has an active core region 11.8 meters in diameter by 7 meters height. There are 1700 tons of graphite blocks in an RBMK-1000 reactor. [13]
The graphite used to construct Fort St. Vrain's core was higher grade and less porous, and thus did not present as much surface area for these reactions to occur. [3] Although system safety was not compromised, frequent operation problems were experienced throughout the reactor systems due to water and corrosion.
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.