Search references for NUCLEAR REACTOR-COOLANT. Phrases containing NUCLEAR REACTOR-COOLANT
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Coolant in a nuclear reactor
A nuclear reactor coolant is a coolant in a nuclear reactor used to remove heat from the nuclear reactor core and transfer it to electrical generators
Nuclear_reactor_coolant
Type of nuclear reactor
reactor (HWR) is a type of nuclear reactor which uses heavy water (D2O, deuterium oxide) as a neutron moderator. It may also use this as the coolant,
Heavy-water_reactor
Device for controlled nuclear reactions
from nuclear fission is passed to a working fluid coolant. In commercial reactors, this drives turbines and electrical generator shafts. Some reactors are
Nuclear_reactor
Type of nuclear reactor
A pressurized water reactor (PWR) is a type of light-water nuclear reactor. PWRs are the most common type of nuclear power reactor, representing almost
Pressurized_water_reactor
Nuclear reactor where the coolant is liquid metal
metal cooled nuclear reactor (LMR) is a type of nuclear reactor where the primary coolant is a liquid metal. Liquid metal cooled reactors were first adapted
Liquid_metal_cooled_reactor
Type of nuclear reactor cooled by molten salt
A molten-salt reactor (MSR) is a class of nuclear fission reactor in which the primary nuclear reactor coolant and/or the fuel is a mixture of molten salt
Molten-salt_reactor
Nuclear reactor that uses moderated neutrons
nuclear reactor coolant. Nuclear fuel, which is a fissile material, usually uranium. Reactor vessel that is a pressure vessel containing the coolant and
Thermal-neutron_reactor
Russian sodium-cooled fast breeder reactor
BN-350 reactor. In 2014, its larger sister reactor, the BN-800 reactor, began operation. The plant is a pool type LMFBR, where the reactor, coolant pumps
BN-600_reactor
Nuclear reactor design
The integral fast reactor (IFR), originally the advanced liquid-metal reactor (ALMR), is a design for a nuclear reactor using fast neutrons and no neutron
Integral_fast_reactor
Type of nuclear reactor, CO2 or He cooled
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
Gas-cooled_reactor
Lead-cooled reactor family designed in Russia
chosen as a coolant for being high-boiling, radiation-resistant, low-activated and at atmospheric pressure. In a traditional nuclear reactor design, the
BREST_(reactor)
Type of nuclear reactor that uses normal water
The light-water reactor (LWR) is a type of thermal-neutron reactor that uses normal water, as opposed to heavy water, as both its coolant and neutron moderator;
Light-water_reactor
Nuclear reactor where fast neutrons maintain a fission chain reaction
A fast-neutron reactor (FNR) or fast-spectrum reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is
Fast-neutron_reactor
Nuclear reactor cooled or moderated by an organic liquid
An Organic nuclear reactor or Organic-cooled reactor (OCR) is a class of nuclear reactor in which the primary coolant or neutron moderator is an organic
Organic_nuclear_reactor
Type of nuclear reactor cooled by molten sodium
fast reactor cooled by liquid sodium-potassium alloy, and demonstrated the concept of nuclear breeding. It also established sodium as the coolant of choice
Sodium-cooled_fast_reactor
Fast-neutron nuclear reactor cooled by molten lead
reactor is a nuclear reactor design that uses molten lead or lead-bismuth eutectic as its coolant. These materials can be used as the primary coolant
Lead-cooled_fast_reactor
Very small nuclear reactor of 1-20 MW capacity
A nuclear microreactor is a type of nuclear reactor which can be easily assembled and transported by road, rail or air. Microreactors are 100 to 1,000
Nuclear_microreactor
Nuclear reactor where water boils in core
electricity-generating nuclear reactor after the pressurized water reactor (PWR). BWRs are thermal neutron reactors, where water is thus used both as a coolant and as
Boiling_water_reactor
Type of nuclear reactor cooled by heat pipes
pipe-cooled reactor (HPR) is a type of nuclear reactor cooled by heat pipes. Using passive heat pipes instead of a pumped nuclear coolant eliminates the
Heat_pipe-cooled_reactor
Reactor accident due to core overheating
A nuclear meltdown (core meltdown, core melt accident, meltdown or partial core melt) is a severe nuclear reactor accident that results in core damage
Nuclear_meltdown
Nuclear reactor design
levels inside the reactor, keeping the nuclear fuel submerged in water and adequately cooled. In events where the reactor coolant pressure boundary remains
Economic Simplified Boiling Water Reactor
Economic_Simplified_Boiling_Water_Reactor
Nuclear power plant design
(the reactor and primary coolant is operated near normal atmospheric pressure), the inability to lose primary coolant (the fuel is the coolant), the
Integral_Molten_Salt_Reactor
Type of nuclear reactor that operates at high temperatures as part of normal operation
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"
High-temperature gas-cooled reactor
High-temperature_gas-cooled_reactor
Russian fast breeder nuclear reactor, operating since 2016
The BN-800 reactor (Russian: реактор БН–800) is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk
BN-800_reactor
Nuclear power system
moderator and normal "light" water as the coolant. The coolant boils in the reactor, like a boiling water reactor, and drives the power-extraction steam
Steam-Generating Heavy Water Reactor
Steam-Generating_Heavy_Water_Reactor
Indian fast breeder nuclear reactor design
India. The indigenously developed reactor achieves a crucial second stage outlined in India's three stage nuclear power program building on the decades
Prototype Fast Breeder Reactor
Prototype_Fast_Breeder_Reactor
Part of a reactor containing the fuel
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
Nuclear_reactor_core
Type of Soviet nuclear power reactor
reactor") is a class of graphite-moderated nuclear power reactor designed and built by the Soviet Union. It is somewhat like a boiling water reactor as
RBMK
German nuclear reactor design proposal with liquid metal cooling loops
separation of liquid metallic fuel and coolant and by the provision for continuous fuel processing beyond Generation IV reactor concepts. The fuel can be a molten
Dual_fluid_reactor
Type of nuclear reactor
The UNGG (Uranium Naturel Graphite Gaz) is an obsolete nuclear power reactor design developed in France. It was graphite moderated, cooled by carbon dioxide
UNGG_reactor
Concept nuclear reactor whose water operates at supercritical pressure
with a BWR, the turbine and reactor pressure vessel are in the same coolant loop, in contrast to a pressurized water reactor (PWR). Most SCWR plants are
Supercritical_water_reactor
Nuclear power plant component
A reactor pressure vessel (RPV) in a nuclear power plant is the pressure vessel containing the nuclear reactor coolant, core shroud, and the reactor core
Reactor_pressure_vessel
Breeder reactor in Idaho, US
world's first breeder reactor. At 1:50 p.m. on December 20, 1951, it became one of the world's first electricity-generating nuclear power plants when it
Experimental Breeder Reactor I
Experimental_Breeder_Reactor_I
graphite reactor (LWGR) is a design of nuclear reactor that uses purified graphite as a neutron moderator and light water (H2O) as a liquid coolant. Due to
Light_water_graphite_reactor
Indian nuclear reactor design
The Bharat Small Modular Reactor, abbreviated as BSMR, is a small modular reactor design being developed in India by the Nuclear Power Corporation of India
Bharat_Small_Modular_Reactor
Type of nuclear fission reactor
A small modular reactor (SMR) is an emergent class of nuclear fission reactors with a rated electrical power of less than 300 megawatts (MWe), which use
Small_modular_reactor
Thermal power station where the heat source is a nuclear reactor
a nuclear reactor heats the reactor coolant. The coolant may be water or gas, or even liquid metal, depending on the type of reactor. The reactor coolant
Nuclear_power_plant
U.S. project 1946–1961
section is instead directed into the nuclear reactor core. The air is heated further, thereby cooling the reactor. The air is then expanded through a turbine
Aircraft_Nuclear_Propulsion
Nuclear power plant in Sosnovy Bor, Leningrad Oblast, Russia
RBMK type of reactor. Despite its age, in 2012 and 2013 the Leningrad NPP took the third place in the annual contest for the Best Nuclear Power Plants
Leningrad_Nuclear_Power_Plant
Type of British nuclear reactor
gas-cooled reactors, using graphite as the neutron moderator and carbon dioxide as coolant. They have been the backbone of the UK's nuclear power generation
Advanced_gas-cooled_reactor
Form of nuclear reactor failure
loss-of-coolant accident (LOCA) is a mode of failure for a nuclear reactor in which the coolant inventory or coolant flow that removes heat from the reactor core
Loss-of-coolant_accident
Decommissioned nuclear reactor in Tennessee, US
The X-10 Graphite Reactor is a decommissioned nuclear reactor at Oak Ridge National Laboratory in Oak Ridge, Tennessee. Formerly known as the Clinton
X-10_Graphite_Reactor
Nuclear reactor design
A pressurized heavy-water reactor (PHWR) is a nuclear reactor that uses heavy water (deuterium oxide D2O) as its coolant and neutron moderator. PHWRs frequently
Pressurized heavy-water reactor
Pressurized_heavy-water_reactor
Nuclear power in Canada is provided by 17 commercial reactors with a net capacity of 12.7 gigawatt (GW), producing a total of 84.6 terawatt-hours (TWh)
Nuclear_power_in_Canada
Small modular reactors (SMR) are much smaller than the current nuclear reactors (300 MWe or less) and have compact and scalable designs which propose
List of small modular reactor designs
List_of_small_modular_reactor_designs
Decommissioned nuclear reactor experiment in Idaho
to 1963 to explore the use of hydrocarbons as coolant, moderator, and reflector materials in power reactor conditions. Such organic fluids are non-corrosive
Organic Moderated Reactor Experiment
Organic_Moderated_Reactor_Experiment
Submarine powered by a nuclear reactor
A nuclear submarine is a submarine powered by a nuclear reactor, but not necessarily nuclear-armed. Nuclear submarines have considerable performance advantages
Nuclear_submarine
Nuclear reactor, Oak Ridge 1965–1969
nuclear cross section data. It was a test reactor simulating the neutronic "kernel" of a type of inherently safer epithermal thorium breeder reactor called
Molten-Salt Reactor Experiment
Molten-Salt_Reactor_Experiment
Small modular nuclear reactor design
Boiling water reactors are nuclear technology that use ordinary light water as a nuclear reactor coolant. Like most boiling water reactors, the BWRX-300
BWRX-300
Type of very-high-temperature reactor
A pebble-bed reactor (PBR) is a type of nuclear reactor where the nuclear fuel is contained within a bed of pyrolytic graphite spheres (pebbles), with
Pebble-bed_reactor
Canadian heavy water nuclear reactor design
generated in the fuel of all nuclear fission reactors. In CANDU reactors, additional tritium is generated in the heavy water coolant and moderator due to neutron
CANDU_reactor
Nuclear power plant in South Korea
second-largest fully operational nuclear generating station by total reactor count and the number of currently operational reactors since 2016, after it exceeded
Kori_Nuclear_Power_Plant
Nuclear power plant in Eurajoki, Finland
cubic metres of radioactive coolant water leaked from the reactor into containment space rooms because a hatch in the reactor refueling pool had not been
Olkiluoto_Nuclear_Power_Plant
Nuclear power plant in Ottawa County, Ohio, United States
reactor coolant to be reclaimed and reinjected into the reactor; the high pressure injection pumps that would reinject such reclaimed reactor coolant;
Davis–Besse Nuclear Power Station
Davis–Besse_Nuclear_Power_Station
Nuclear power safety method that does not require electrical power nor intervention
Passive nuclear safety is a design approach for safety features, implemented in a nuclear reactor, that does not require any active intervention on the
Passive_nuclear_safety
Chemical compound
reactor was destroyed in 2012. The United States' experimental SNAP-10A satellite, which was the first nuclear reactor in space, used NaK as coolant.
Sodium–potassium_alloy
Nuclear plant in Zhejiang, China
to 2017. In January 2017 China National Nuclear Corporation (CNNC) announced that the final reactor coolant pump had been installed with start of operations
Sanmen_Nuclear_Power_Station
Decommissioned nuclear power plant in Ukraine
reactor designs, such as the VVER pressurized water reactor. Originally named the Chernobyl Nuclear Power Plant of V. I. Lenin after the founding leader
Chernobyl_Nuclear_Power_Plant
Nuclear power plant in California, US
California. The reactor operated from 1957 to 1964. On July 12, 1957 the Sodium Reactor Experiment became the first nuclear reactor in California to
Sodium_Reactor_Experiment
1979 nuclear accident in Pennsylvania
Mile Island accident was a partial nuclear meltdown of the Unit 2 reactor (TMI-2) of the Three Mile Island Nuclear Generating Station, located on the
Three_Mile_Island_accident
Classes of nuclear reactors used by the United States Navy
119.519361°W / 46.565222; -119.519361 United States naval reactors are nuclear reactors used by the United States Navy aboard certain ships to generate
United_States_naval_reactors
Decommissioned nuclear power plant located in Lubmin, Germany
largest nuclear power station in East Germany before it was shut down shortly after the German reunification.[citation needed] The plant's reactors were
Greifswald Nuclear Power Plant
Greifswald_Nuclear_Power_Plant
Ballistic missile submarine
to avoid a nuclear meltdown. Sacrificing their own lives, the engineering crew jury-rigged a secondary coolant system and kept the reactor from a meltdown
Soviet_submarine_K-19
Soviet nuclear reactor for use in space
The TOPAZ nuclear reactor is a lightweight nuclear reactor developed for long term space use by the Soviet Union. Cooled by liquid metal, it uses a high-temperature
TOPAZ_nuclear_reactor
Nuclear power station in Russia
typical enrichment in other Russian reactors is in the range of 3–4% 235U. BN-600 reactors use liquid sodium as a coolant. The station lacks a containment
Beloyarsk Nuclear Power Station
Beloyarsk_Nuclear_Power_Station
Severe events involving radioactive materials
causes harm. In a large nuclear reactor, a loss of coolant accident can damage the core: for example, at Three Mile Island Nuclear Generating Station a recent
Nuclear and radiation accidents and incidents
Nuclear_and_radiation_accidents_and_incidents
United States, nuclear power is provided by 96 commercial reactors with a net capacity of 98 gigawatts (GW), with 65 pressurized water reactors and 31 boiling
Nuclear power in the United States
Nuclear_power_in_the_United_States
Type of nuclear reactor that uses molten material as fuel
steam turbine or closed-cycle gas turbine. Molten-salt-fueled reactors (MSRs) supply the nuclear fuel mixed into a molten salt. They should not be confused
Liquid fluoride thorium reactor
Liquid_fluoride_thorium_reactor
New nuclear reactor technologies under development
Generation IV (Gen IV) reactors are nuclear reactor design technologies that are envisioned as successors of generation III reactors. The Generation IV International
Generation_IV_reactor
Form of water
hydrogen isotope. Heavy water contains deuterium atoms and is used in nuclear reactors. Semiheavy water (HDO) is more common than pure heavy water, while
Heavy_water
UK Ministry of Defence in Scotland
prototype nuclear reactors, trialling five different types of submarine reactor core. The site is located adjacent to the Dounreay civil nuclear site. When
Vulcan Naval Reactor Test Establishment
Vulcan_Naval_Reactor_Test_Establishment
Pressurised water reactor series
The Rolls-Royce Pressurised Water Reactor (PWR) series has powered the Royal Navy's nuclear submarines since the Valiant class, commissioned in 1966.
Rolls-Royce_PWR
Power plant in the Czech Republic
Coolant outlet temperature: approx. 320 °C (608F) Coolant flow through reactor: 23.5 m3/s Number per reactor unit: 4 Steam delivered per one generator: 1,470
Temelín_Nuclear_Power_Station
Simulates a nuclear reactor's coolant system and core
a nuclear reactor's coolant system and the reactor core for various operational transients and postulated accidents that might occur in a nuclear reactor
RELAP5-3D
Nuclear reactor in Ohio, United States
The Piqua Nuclear Power Facility was an organic-cooled and moderated nuclear reactor which operated just outside the southern city limits of Piqua, Ohio
Piqua_Nuclear_Power_Facility
Material in core during nuclear meltdown
created in a nuclear reactor core during a nuclear meltdown accident. Resembling lava in consistency, it consists of a mixture of nuclear fuel, fission
Corium_(nuclear_reactor)
Type of nuclear 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
Graphite-moderated_reactor
Soviet submarine commander
submarine K-19 in July 1961 during the Hotel class submarine's nuclear-reactor coolant leak. Zateyev and the actions of his crew managed to avert disaster
Nikolai_Vladimirovich_Zateyev
Naval nuclear reactor
The A2W reactor is a naval nuclear reactor used by the United States Navy to provide electricity generation and propulsion on warships. The A2W designation
A2W_reactor
UK experimental HTR, operated from 1965 to 1976
construction and operation of experimental and research nuclear reactors. Dragon used helium gas as the coolant and graphite as the neutron moderator. Fuel was
Dragon_reactor
domestically developed Magnox and their successor AGR reactors with graphite moderator and CO2 coolant but the last of those are nearing the end of their
Nuclear power in the United Kingdom
Nuclear_power_in_the_United_Kingdom
2011 nuclear accident in Japan
the heat exchanger by the reactor pressure, and the condensed coolant would be fed back into the vessel by gravity. Each reactor was initially designed to
Fukushima_nuclear_accident
Naturally occurring uranium self-sustaining nuclear chain reactions
A natural nuclear fission reactor is a uranium deposit where self-sustaining nuclear chain reactions occur through natural geological processes rather
Natural nuclear fission reactor
Natural_nuclear_fission_reactor
Safety system in nuclear reactors
heat Nuclear reactor coolant Light-water reactor Auxiliary feedwater Nuclear reactor safety system Boiling water reactor safety systems Reactor Concepts
Residual_heat_removal_system
Nuclear reactor generating more fissile material than it consumes
A breeder reactor is a nuclear reactor that generates more fissile material than it consumes. These reactors can be fueled with more-commonly available
Breeder_reactor
Type of nuclear reactor cooled by a gas
which allows for better coolant circulation than traditional fuel assemblies. The reactors are intended for use in nuclear power plants to produce electricity
Gas-cooled_fast_reactor
Russian nuclear pressurized water reactors
The VM reactor (Russian: реактор ВМ) is type of various series of nuclear pressurized water reactors (PWR). They were used singly or in pairs to power
VM_reactor
Radioisotope production reactor
The Dhruva reactor is India's largest nuclear research reactor. It was the first nuclear reactor in Asia proper. Located in the Mumbai suburb of Trombay
Dhruva_reactor
Fast breeder nuclear reactor under development in Russia
The BN-1200 reactor is a sodium-cooled fast breeder reactor project, under development by OKBM Afrikantov at Beloyarsk Nuclear Power Station in Zarechny
BN-1200_reactor
Chemical compound
It is both a nuclear reactor coolant and solvent for fertile or fissile material. It served both purposes in the Molten-Salt Reactor Experiment (MSRE)
FLiBe
Idaho National Laboratory research neutron source
environment while accelerating the nuclear conditions. The ATR is a pressurized light water reactor (LWR), using water as both coolant and moderator. The core is
Advanced_Test_Reactor
Nuclear power plant in Romania
reactor technology from AECL, using heavy water produced at Drobeta-Turnu Severin as its neutron moderator and as its coolant agent. By using nuclear
Cernavodă_Nuclear_Power_Plant
Rocket-propelled by exhausted coolant of a gas-cooled nuclear reactor
reactor rockets are a conceptual type of rocket that is propelled by the exhausted coolant of a gaseous fission reactor. The nuclear fission reactor core
Gas_core_reactor_rocket
Indian nuclear reactor design
PHWRs the tubes are vertical rather than horizontal. The reactor core contains 452 coolant channels, of which 424 contain a fuel cluster. Each cluster
Advanced_heavy-water_reactor
commercial nuclear reactors in the world, sorted by country, with operational status. The list only includes civilian nuclear power reactors used to generate
List of commercial nuclear reactors
List_of_commercial_nuclear_reactors
FLiNaK also could see potential use as a coolant in the very high temperature reactor, a type of nuclear reactor. FLiNaK salt was researched heavily during
FLiNaK
Navy with ships powered by nuclear energy
unrelated to their reactor plants and still lie on the Atlantic sea floor. [citation needed] K-8 (1960; November-class submarine; loss of coolant) K-19 (1961;
Nuclear_navy
Topics referred to by the same term
internal combustion engine cooling Cooling systems for nuclear powerplants, using nuclear reactor coolant Cooling systems for computer equipment, see computer
Cooling_system
Emergency shutdown of a nuclear reactor
A scram or SCRAM is an emergency shutdown of a nuclear reactor effected by terminating the fission reaction. It is also the name that is given to the
Scram
Family of nuclear research reactors
Kritical Experiment) is a family of low-energy, tank-in-pool type nuclear research reactors designed by Atomic Energy of Canada Limited (AECL) beginning in
SLOWPOKE_reactor
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NUCLEAR REACTOR-COOLANT
NUCLEAR REACTOR-COOLANT
Boy/Male
Spanish American Shakespearean Greek Latin
Tenacious.
Boy/Male
Indian
Creator
Boy/Male
Arthurian Legend
Father of Arthur.
Surname or Lastname
English
English : probably a habitational name from clere, a component of several place names in north Hampshire (Highclere, Burghclere, Kingsclere). This is of uncertain origin, probably from a Celtic stream name meaning ‘bright’ (cognate with Latin clarus ‘clear’, ‘bright’).English and Irish : variant of Clare.Translation of German Klar 1.
Girl/Female
Latin
Sweet.
Boy/Male
Muslim
Creator
Girl/Female
Assamese, Gujarati, Hindu, Indian, Kannada, Malayalam, Marathi, Rajasthani, Sanskrit, Sindhi, Tamil, Telugu
Creator
Male
Arthurian
, sir Hector de Maris; (defender).
Male
Arthurian
, defender.
Boy/Male
Tamil
Creator
Boy/Male
Latin
Son of Azeus.
Boy/Male
American, Australian, British, Chinese, Christian, Danish, Dutch, English, French, German, Greek, Italian, Latin, Portuguese, Shakespearean, Spanish
Steadfast; Anchor; Holds Fast; Star; Coined from Esther Vanhomrigh; Tenacious; Defend; Hold Fast; Coined from Esther Vanho
Girl/Female
Hindu
Creator
Girl/Female
Tamil
Rachiyata | ரசியதா
Creator
Rachiyata | ரசியதா
Boy/Male
Christian & English(British/American/Australian)
Steadfast
Boy/Male
Muslim
Creator
Girl/Female
Hindu, Indian, Malayalam, Marathi, Tamil
Creator
Surname or Lastname
Scottish
Scottish : Anglicized form of the Gaelic personal name Eachann (earlier Eachdonn, already confused with Norse Haakon), composed of the elements each ‘horse’ + donn ‘brown’.English : found in Yorkshire and Scotland, where it may derive directly from the medieval personal name. According to medieval legend, Britain derived its name from being founded by Brutus, a Trojan exile, and Hector was occasionally chosen as a personal name, as it was the name of the Trojan king’s eldest son. The classical Greek name, HektÅr, is probably an agent derivative of Greek ekhein ‘to hold back’, ‘hold in check’, hence ‘protector of the city’.German, French, and Dutch : from the personal name (see 2 above). In medieval Germany, this was a fairly popular personal name among the nobility, derived from classical literature. It is a comparatively rare surname in France.
Male
English
 Anglicized form of Scottish Gaelic Eachann, HECTOR means "brown horse." Compare with another form of Hector.
Boy/Male
Tamil
Creator
NUCLEAR REACTOR-COOLANT
NUCLEAR REACTOR-COOLANT
NUCLEAR REACTOR-COOLANT
NUCLEAR REACTOR-COOLANT
NUCLEAR REACTOR-COOLANT
NUCLEAR REACTOR-COOLANT
NUCLEAR REACTOR-COOLANT
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