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Graphite Moderated Reactors
:''"Graphite reactor" directs here. For the graphite reactor at Oak Ridge National Laboratory, see X-10 Graphite Reactor.'' A graphite-moderated reactor is a nuclear reactor that uses carbon as a neutron moderator, which allows natural uranium to be used as nuclear fuel. The first artificial nuclear reactor, the Chicago Pile-1, used nuclear graphite as a moderator. Graphite-moderated reactors were involved in two of the best-known nuclear disasters: an untested graphite annealing process contributed to the Windscale fire (but the graphite itself did not catch fire), while a graphite fire during the Chernobyl disaster contributed to the spread of radioactive material. Types Several types of Nuclear graphite, graphite-Neutron moderation, moderated nuclear reactors have been used in commercial electricity generation: *Gas-cooled reactors **Magnox **UNGG reactor **Advanced gas-cooled reactor (AGR) *Water-cooled reactors **RBMK **MKER **EGP-6 **N-Reactor, Hanford N-Reactor (dual us ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Nuclear Reactor Uranium Pile (30502443888)
Nuclear may refer to: Physics Relating to the Atomic nucleus, nucleus of the atom: *Nuclear engineering *Nuclear physics *Nuclear power *Nuclear reactor *Nuclear weapon *Nuclear medicine *Radiation therapy *Nuclear warfare Mathematics *Nuclear space *Nuclear operator *Nuclear congruence *Nuclear C*-algebra Biology Relating to the Cell nucleus, nucleus of the cell: * Nuclear DNA Society *Nuclear family, a family consisting of a pair of adults and their children Music *Nuclear (band), "Nuclear" (band), chilean thrash metal band *Nuclear (Ryan Adams song), "Nuclear" (Ryan Adams song), 2002 *"Nuclear", a song by Mike Oldfield from his ''Man on the Rocks'' album *Nu.Clear (EP), ''Nu.Clear'' (EP) by South Korean girl group CLC Films *Nuclear (film), ''Nuclear'' (film), a 2022 documentary by Oliver Stone. See also *Nucleus (other) *Nucleolus *Nucleation *Nucleic acid *Nucular * * {{Disambiguation ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Advanced Gas-cooled Reactor
The advanced gas-cooled reactor (AGR) is a type of nuclear reactor designed and operated in the United Kingdom. These are the generation II reactor, second generation of British gas-cooled reactors, using Nuclear graphite, graphite as the neutron moderator and carbon dioxide as coolant. They have been the backbone of the UK's nuclear power generation fleet since the 1980s. The AGR was developed from the Magnox reactor, the UK's first-generation reactor design. The first Magnox design had been optimised for generating plutonium, and for this reason it had features that were not the most economic for power generation. Primary among these was the requirement to run on natural uranium, which required a coolant with a low neutron cross section, in this case carbon dioxide, and an efficient neutron moderator, graphite. The Magnox design also ran relatively cool gas temperatures compared to other power-producing designs, which resulted in less efficient steam conditions. The AGR design r ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Prismatic Fuel Reactor
A gas-cooled reactor (GCR) is a nuclear reactor that uses graphite as a neutron moderator and a gas (carbon dioxide or helium in extant designs) as coolant. Although there are many other types of reactor cooled by gas, the terms ''GCR'' and to a lesser extent ''gas cooled reactor'' are particularly used to refer to this type of reactor. The GCR was able to use natural uranium as fuel, enabling the countries that developed them to fabricate their own fuel without relying on other countries for supplies of enriched uranium, which was at the time of their development in the 1950s only available from the United States or the Soviet Union. The Canadian CANDU reactor, using heavy water as a moderator, was designed with the same goal of using natural uranium fuel for similar reasons. Design considerations Historically thermal spectrum graphite-moderated gas-cooled reactors mostly competed with light water reactors, ultimately losing out to them after having seen some deployment in Brit ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Very High Temperature Reactor
A high-temperature gas-cooled reactor (HTGR) is a type of gas-cooled nuclear reactor which uses uranium fuel and graphite moderation to produce very high reactor core output temperatures. All existing HTGR reactors use helium coolant. The reactor core can be either a "prismatic block" (reminiscent of a conventional reactor core) or a " pebble-bed" core. China Huaneng Group currently operates HTR-PM, a 250 MW HTGR power plant in Shandong province, China. The high operating temperatures of HTGR reactors potentially enable applications such as process heat or hydrogen production via the thermochemical sulfur–iodine cycle. A proposed development of the HTGR is the Generation IV very-high-temperature reactor (VHTR) which would initially work with temperatures of 750 to 950 °C. History The use of a high-temperature, gas-cooled reactor for power production was proposed by in 1944 by Farrington Daniels, then associate director of the chemistry division at the Univer ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Pebble-bed Reactor
The pebble-bed reactor (PBR) is a design for a graphite- moderated, gas-cooled nuclear reactor. It is a type of very-high-temperature reactor (VHTR), one of the six classes of nuclear reactors in the Generation IV initiative. The basic design features spherical fuel elements called pebbles. These tennis ball-sized elements (approx. in diameter) are made of pyrolytic graphite (which acts as the moderator), and contain thousands of fuel particles called tristructural-isotropic (TRISO) particles. These TRISO particles consist of a fissile material (such as ) surrounded by a ceramic coating of silicon carbide for structural integrity and fission product containment. Thousands of pebbles are amassed to create a reactor core. The core is cooled by a gas that does not react chemically with the fuel elements, such as helium, nitrogen or carbon dioxide. Other coolants such as FLiBe (molten ) have been suggested. The pebble bed design is passively safe. Because the reactor is de ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Fort St
A fortification (also called a fort, fortress, fastness, or stronghold) is a military construction designed for the defense of territories in warfare, and is used to establish rule in a region during peacetime. The term is derived from Latin ("strong") and ("to make"). From very early history to modern times, defensive walls have often been necessary for cities to survive in an ever-changing world of invasion and conquest. Some settlements in the Indus Valley Civilization were the first small cities to be fortified. In ancient Greece, large cyclopean stone walls fitted without mortar had been built in Mycenaean Greece, such as the ancient site of Mycenae. A Greek '' phrourion'' was a fortified collection of buildings used as a military garrison, and is the equivalent of the Roman castellum or fortress. These constructions mainly served the purpose of a watch tower, to guard certain roads, passes, and borders. Though smaller than a real fortress, they acted as a border ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
THTR-300
The THTR-300 was a thorium cycle high-temperature nuclear reactor rated at 300 MW electric (THTR-300) in Hamm-Uentrop, Germany. It started operating in 1983, synchronized with the grid in 1985, operated at full power in February 1987 and was shut down on 1 September 1989. The THTR-300 served as a prototype high-temperature reactor (HTR) to use the TRISO pebble fuel produced by the AVR, an experimental pebble bed operated by VEW (Vereinigte Elektrizitätswerke Westfalen). The THTR-300 cost €2.05 billion and was predicted to cost an additional €425 million through December 2009 in decommissioning and other associated costs. The German state of North Rhine Westphalia, Federal Republic of Germany, and Hochtemperatur-Kernkraftwerk GmbH (HKG) financed the THTR-300’s construction. History On 4 June 1974, the Council of the European Communities established the Joint Undertaking "Hochtemperatur-Kernkraftwerk GmbH" (HKG). The electrical generation part of the THTR-300 was fin ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Peach Bottom Nuclear Generating Station
The Peach Bottom Atomic Power Station is an American nuclear power plant that is located southeast of Harrisburg in Peach Bottom Township, York County, Pennsylvania. Situated close to the Susquehanna River, it is three miles north of the Maryland border. History The Philadelphia Electric Company (later "PECO") was a pioneer in the commercial nuclear industry when it ordered Peach Bottom 1 in 1958. The U.S.'s first nuclear power plant (the Shippingport Reactor) had gone on line a year earlier. Peach Bottom Unit 1 was an experimental helium-cooled, graphite-moderated reactor. The reactor was fueled by a mixed 232Th- 235U fuel. It operated from 1966 to 1974. Peach Bottom 2 and 3, General Electric boiling water reactors, went on-line in 1974, and are still in operation on the 620-acre (2.5 km2) site today. Both Units 2 and 3, originally rated at 3,514 megawatts thermal (MWth), equivalent to about 1,180 megawatts of electricity (MWe) each, were uprat ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
AVR Reactor
The AVR reactor () was a prototype pebble-bed reactor, located immediately adjacent to Jülich Research Centre in West Germany, constructed in 1960, grid connected in 1967 and shut down in 1988. It was a 15 MWe, 46 MWt test reactor used to develop and test a variety of fuels and machinery. The AVR was based on the concept of a "Daniels pile" by Farrington Daniels, the inventor of pebble bed reactors. Rudolf Schulten is commonly recognized as the intellectual father of the reactor. A consortium of 15 community electric companies owned and operated the plant. Over its lifetime the reactor had many accidents, earning it the name "shipwreck." From 2011 to 2014, outside experts examined the historical operations and operational hazards and described serious concealed problems and wrongdoings in their final 2014 report. For example, in 1978 operators bypassed reactor shutdown controls to delay an emergency shutdown during an accident for six days. In 2014 the JRC and AVR publicly ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
Dragon Reactor
Dragon was an experimental high temperature gas-cooled reactor at Winfrith in Dorset, England, operated by the United Kingdom Atomic Energy Authority (UKAEA). Its purpose was to test fuel and materials for the European High Temperature Reactor programme, which was exploring the use of tristructural-isotropic (TRISO) fuel and gas cooling for future high-efficiency reactor designs. The project was built and managed as an Organisation for Economic Co-operation and Development/ Nuclear Energy Agency international project. In total, 13 countries were involved in its design and operation during the project lifetime. Originally conceived as a small research reactor, during the design phase it grew larger. The choice of helium coolant was made after a long debate within the UKAEA between proponents of helium and carbon dioxide, with helium ultimately selected. Groundbreaking occurred in 1960. It operated from 1965 to 1976, and is generally considered extremely successful. Dragon's con ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
ADE-2
The ADE-2 is a dual use water-cooled thermal graphite-moderated reactor. The reactor was dual-purpose - producing weapons-grade plutonium and providing heat and electricity. The RBMK series nuclear reactors are based off the ADE series reactors. History Construction started in December 1963. The reactor was shut down in April 2010. The scope of decommissioning was much greater than with AD and ADE-1, which were single-purpose and performed only defense tasks. In 2021 it was decided to make ADE-2 a museum exhibition. Other similar types These two sources show slightly different date of start and shutdown. Legacy AD and ADE-1 are almost decommissioned. ADE-3, ADE-4, and ADE-5 were being decommissioned as of 2024. See also * MBIR - multi-loop research reactor intends to replace BOR-60. In construction since 2015, est. completion in 2027. * RBMK - is a class of graphite-moderated nuclear power reactor designed and built by the Soviet Union The Union of Soviet ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
N-Reactor
The N-Reactor was a water/graphite-neutron moderator, moderated nuclear reactor constructed during the Cold War and operated by the United States, U.S. government at the Hanford Site in Washington (state), Washington; it began production in 1963. It was a one-of-a-kind design in the U.S., being both a plutonium production reactor for nuclear weapons and, from 1966, producing steam to allow production of electricity to feed the civilian power grid via the Energy Northwest, Washington Public Power Supply System or WPPSS. The power rating of the N-Reactor was 4000 MWt, with a power output of 800 MWe at the power generating plant. In an improvement on the earlier Hanford reactors, N-Reactor was built with a confinement building (although not a containment building). In the event of an accidental release of steam, air and steam would vent through filters that confined any radioactive particles present. It was partially moderated with graphite, but had a negative void coefficient due t ... [...More Info...] [...Related Items...] OR: [Wikipedia] [Google] [Baidu] |
