The A1B reactor plant is still in the design phase, but is slated to be installed in the U.S. Navy's next class of nuclear aircraft carriers. ...more on Wikipedia about "A1B reactor"
The A1W nuclear reactor was a Westinghouse-built naval reactor power plant, installed in the Naval Reactor Facility in the desert of Idaho. It first operated in October 1958. ...more on Wikipedia about "A1W reactor"
The A2W reactor designation for the nuclear reactors on the USS Enterprise (CVN-65) stands for: ...more on Wikipedia about "A2W reactor"
The A3W reactor was intended for use aboard the USS John F. Kennedy (CV-67). This was a four nuclear reactor per ship design to reduce the cost involved in the construction and operation of the USS Enterprise (CVN-65), with its eight reactors. ...more on Wikipedia about "A3W reactor"
An A4W reactor is a type of nuclear reactor in use aboard the United States Navy's Nimitz-class supercarriers, capable of producing 140,000 shaft horsepower (104 MW) of energy, and with a normal fuel lifespan of 10 years and a core lifespan of 50 years. The nuclear fuel was originally 93% U235, but current technology uses 20-25% U235. The fuel is not UO2, but rather a metal- zirconium alloy. The reactor uses an internal neutron shield to maintain long term integrity. ...more on Wikipedia about "A4W reactor"
The Advanced Boiling Water Reactor (ABWR) is an improved design of boiling water reactor. The ABWR was designed by General Electric. ...more on Wikipedia about "Advanced Boiling Water Reactor"
The Advanced CANDU Reactor (ACR) is an AECL Technologies’ design and is the evolutionary development of existing CANDU reactors. It is a light-water-cooled reactor that incorporates features of both Pressurised Heavy Water Reactors (PHWR) and Advanced Pressurized Water Reactors (APWR) technologies. ...more on Wikipedia about "Advanced CANDU Reactor"
An Advanced Gas Cooled Reactor (AGR) is a type of nuclear reactor. These are the second generation of British gas-cooled reactors, using graphite as the neutron moderator and carbon dioxide as coolant. The fuel is uranium oxide pellets, enriched to 2.5-3.5%, in stainless steel tubes. The carbon dioxide circulates through the core, reaching 640°C and then passes through boiler (steam generator) assemblies outside the core but still within the steel lined, reinforced concrete pressure vessel. Control rods penetrate the moderator and a secondary shutdown system involves injecting nitrogen into the coolant or releasing boron ball shutdown devices. ...more on Wikipedia about "Advanced gas-cooled reactor"
Advanced Pressurized Water Reactor is a type of nuclear reactor which is an improved version of existing Pressurized Water Reactor types. ...more on Wikipedia about "Advanced Pressurized Water Reactor"
The US Aircraft Reactor Experiment (ARE) was a 2.5 MW thermal nuclear reactor experiment designed to attain a high power density for use as an engine in a nuclear powered bomber. It led to the Heat Transfer Reactor Experiment, of which there were three iterations: HTRE-l, HTRE-2, and HTRE-3. It used the molten fluoride salt - F4- F4 (53-41-6 mol%) as fuel and was moderated by beryllium oxide (BeO), liquid sodium as a secondary coolant, and it had a peak temperature of 860 °C, it operated for a 1000hr cycle in 1954. It was the first molten salt reactor. Work on this project in the US stopped after ICBMs made it obsolete. The designs for its engines can currently be viewed at the EBR-I memorial building. ...more on Wikipedia about "Aircraft Reactor Experiment"
Aqueous Homogenous Reactors (AHR) are a type of nuclear reactor in which soluble nuclear salts (usually uranium sulfate or uranium nitrate) have been dissolved in water. The fuel is mixed with the coolant and the moderator, thus the name "Homogenous" ('mixed together') The water can be either heavy water or light water, both which need be very pure. A heavy water aqueous homogenous reactor can achieve criticality (turn on) with natural uranium dissolved as uranium sulfate. Thus, no enriched uranium is needed for this reactor. The Heavy Water versions have the lowest specific fuel requirements (least amount of nuclear fuel is required to start them). Even in light water versions less than 1 pound (454 grams) of Plutonium-239 or Uranium-233 is needed for operation. Neutron economy in the heavy water versions is the highest of all reactor designs. ...more on Wikipedia about "Aqueous Homogeneous Reactor"
The Argonaut class reactor is a design of small nuclear research reactor. Many have been built throughout the world, over a wide range of power levels. Its functions are to teach nuclear reactor theory, nuclear physics and for use in engineering laboratory experiments. ...more on Wikipedia about "Argonaut class reactor"
(Astra (reactor)) A type of nuclear research reactor built in Seibersdorf, Austria. The acronym stands for Adaptierter Schwimmbecken-Typ-Reaktor Austria (Adapted swimming pool type reactor Austria). ...more on Wikipedia about "Astra (reactor)"
The B-Reactor at Hanford Site, Washington, was the first large scale plutonium production reactor ever built. The project was commissioned under the Manhattan Project, during World War II, to develop the first atomic bombs. The reactor was designed and built by the DuPont company based on experimental designs tested by Enrico Fermi at the University of Chicago. The B-Reactor was completed in September of 1944, and was designed to operate at 250 kilowatts. The reactor was graphite moderated and water cooled. The plutonium for the Trinity device, tested in New Mexico, and the Fat Man bomb, later dropped on Nagasaki, Japan, ws created by irradiating Uranium-238 in B-Reactor. The B-Reactor operated through December of 1968. It is now in "interim safe storage" mode and is being turned into a museum. ...more on Wikipedia about "B-Reactor"
A boiling water reactor (BWR) is a light water reactor design used in some nuclear power stations. It has many similarities to the pressurized water reactor (PWR), except that in a BWR the steam going to the turbine is produced in the reactor core rather than in a steam generator or heat exchanger. In a BWR there is only a single circuit in which the water is at lower pressure than in a PWR (about 75 times atmospheric pressure) so that it boils in the core at about 285°C. The reactor is designed to operate with 12–15% of the water in the top part of the core as steam, resulting in less moderation, lower neutron efficiency and lower power density than in the bottom part of the core. The BWR design is very safe because it is a PWR which has been designed to operate permanently under fault conditions. The fault which is being considered is a coolant leak in a PWR. ...more on Wikipedia about "Boiling water reactor"
The BORAX Experiments, boiling reactor experiments, were a series of tests using the BORAX-I nuclear reactor which proved Samuel Untermyer's 1952 theory that a reactor using direct boiling of water would be practical, rather than unstable because of the bubble formation in the core. Subsequently the reactor was used for power excursion tests which showed that rapid conversion of steam to water would safely control the reaction. The final, deliberately destructive, test produced an unexpectedly large power excursion and provided additional useful data to improve mathematical models. The tests proved key safety principles of the design of modern nuclear power reactors. Design power of BORAX-I was 1.4 megawatts thermal. ...more on Wikipedia about "BORAX experiments"
BREN Tower is a guyed steel framework mast, 465 meters (1,527 feet) high, on the Nevada Test Site in Nevada, USA. "BREN" stands for "Bare Reactor Experiment, Nevada." ...more on Wikipedia about "BREN Tower"
Calandria is the reactor core of the CANDU reactor. The Calandria contains heavy water (Deuterium oxide), a moderator used to slow the speed of the neutrons to help achieve nuclear fission. ...more on Wikipedia about "Calandria"
The CANDU reactor is a pressurized- heavy water (PHWR), natural uranium (i.e. unenriched) power reactor designed in the late 1950s and 1960s by a partnership between Atomic Energy of Canada Limited (AECL) and the Hydro-Electric Power Commission of Ontario (now known as Ontario Power Generation), as well as several private industry participants. The acronym "CANDU", a registered trademark of Atomic Energy of Canada Limited, stands for "CANada Deuterium Uranium". This is a reference to its deuterium oxide ( heavy water) moderator and its use of natural uranium fuel. All current power reactors in Canada are of the CANDU type. Canada markets the power-reactor product abroad. ...more on Wikipedia about "CANDU reactor"
On December 2, 1942, the world's first artificial self-sustaining nuclear chain reaction took place in the world's first nuclear reactor, Chicago Pile-1, shortened as CP-1, built on a racquets court under the abandoned west stands of the Alonzo Stagg Field stadium on the University of Chicago campus. Operation of CP-1 was terminated in February 1943 and the nuclear reactor dismantled and moved to the laboratory's Palos Park site A. It was reconstructed using CP-1 materials but enlarged with a radiation shield and named CP-2. It began operation in March 1943. ...more on Wikipedia about "Chicago Pile-1"
CIRUS (Canadian-Indian-U.S.) reactor. A research reactor at the Bhabha Atomic Research Center (BARC) in Trombay near Mumbai Bombay in India. CIRUS was supplied by Canada in 1954, but uses heavy water supplied by the U.S. (hence its name). It is the second oldest reactor in India. It is modeled on the Canadian Chalk River National Research X-perimental NRX reactor. The 40 MWt reactor burns natural uranium fuel, while using heavy water (deuterium) as a moderator. It is a tank reactor type with a core size of 3.14 m(H)x2.67 m (D). It first went critical July 10, 1960. ...more on Wikipedia about "CIRUS reactor"
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The D1G reactor was a prototype nuclear fission reactor constructed for the U.S. Department of Energy's Office of Naval Reactors as part of the Naval Nuclear Propulsion Program. ...more on Wikipedia about "D1G reactor"
The D2G nuclear reactor was found on all US nuclear cruisers with the exception of the USS Long Beach (CGN-9). ...more on Wikipedia about "D2G reactor"
DIDO was a nuclear reactor at the Atomic Energy Research Establishment at Harwell, Oxfordshire in the United Kingdom. It used enriched uranium metal fuel, and heavy water as both neutron moderator and primary coolant. There was also a graphite neutron reflector surrounding the core. ...more on Wikipedia about "DIDO"
Experimental Breeder Reactor Number One (EBR-I) has the distinction of being the world's first experimental nuclear power plant. EBR-I is a Registered National Historic U.S. Landmark in the desert about 18 miles southeast of Arco, Idaho. On December 20, 1951, a successful experiment at EBR-I proved the viability of nuclear power by illuminating four light bulbs. Thus the facility truly is the world's birthplace of usable atomic energy from a nuclear reactor. ...more on Wikipedia about "EBR-I" www.shortopedia.com - now! shortopedia
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