:''"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
A nuclear reactor is a device used to initiate and control a fission nuclear chain reaction or nuclear fusion reactions. Nuclear reactors are used at nuclear power plants for electricity generation and in nuclear marine propulsion. Heat fr ...
that uses carbon as a
neutron moderator, which allows natural
uranium
Uranium is a chemical element with the symbol U and atomic number 92. It is a silvery-grey metal in the actinide series of the periodic table. A uranium atom has 92 protons and 92 electrons, of which 6 are valence electrons. Uranium is weak ...
to be used as
nuclear fuel.
The first artificial nuclear reactor, the
Chicago Pile-1, used
nuclear graphite
Nuclear graphite is any grade of graphite, usually synthetic graphite, manufactured for use as a moderator or reflector within a nuclear reactor. Graphite is an important material for the construction of both historical and modern nuclear reactor ...
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
The Windscale fire of 10 October 1957 was the worst nuclear accident in the United Kingdom's history, and one of the worst in the world, ranked in severity at level 5 out of a possible 7 on the International Nuclear Event Scale. The fire was in ...
(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
graphite
Graphite () is a crystalline form of the element carbon. It consists of stacked layers of graphene. Graphite occurs naturally and is the most stable form of carbon under standard conditions. Synthetic and natural graphite are consumed on lar ...
-
moderated
Moderation is the process of eliminating or lessening extremes. It is used to ensure normality throughout the medium on which it is being conducted. Common uses of moderation include:
*Ensuring consistency and accuracy in the marking of stud ...
nuclear reactor
A nuclear reactor is a device used to initiate and control a fission nuclear chain reaction or nuclear fusion reactions. Nuclear reactors are used at nuclear power plants for electricity generation and in nuclear marine propulsion. Heat fr ...
s have been used in commercial
electricity generation
Electricity generation is the process of generating electric power from sources of primary energy. For utilities in the electric power industry, it is the stage prior to its delivery ( transmission, distribution, etc.) to end users or its s ...
:
*
Gas-cooled 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 ...
s
**
Magnox
Magnox is a type of nuclear power/production reactor that was designed to run on natural uranium with graphite as the moderator and carbon dioxide gas as the heat exchange coolant. It belongs to the wider class of gas-cooled reactors. The n ...
**
UNGG 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, and fueled with natural uranium metal. The first generation of French nuclear pow ...
**
Advanced gas-cooled reactor (AGR)
*Water-cooled reactors
**
RBMK
The RBMK (russian: реактор большой мощности канальный, РБМК; ''reaktor bolshoy moshchnosti kanalnyy'', "high-power channel-type reactor") is a class of graphite-moderated nuclear power reactor designed and buil ...
**
MKER
The MKER (russian: МКЭР, Многопетлевой Канальный Энергетический Реактор: ''Mnogopetlevoy Kanalynyi Energeticheskiy Reaktor'', translation: ''multi-loop pressure tube power reactor'') is a Russian thi ...
**
EGP-6 The EGP-6 is a Russian small nuclear reactor design. It is a scaled down version of the RBMK design. As the RBMK, the EGP-6 uses water for cooling and graphite as a neutron moderator. EGP is a Russian acronym but translated into English stand for P ...
*High-temperature gas-cooled reactors (past)
**
Dragon reactor
DRAGON Reactor Experiment (DRE) was an experimental high temperature gas-cooled reactor at Winfrith in Dorset, England, an experimental reactor of the Organisation for Economic Co-operation and Development (O.E.C.D) High Temperature Reactor Projec ...
**
AVR
**
Peach Bottom Nuclear Generating Station
Peach Bottom Atomic Power Station, a nuclear power plant, is located southeast of Harrisburg in Peach Bottom Township, York County, Pennsylvania, on the Susquehanna River three miles north of the Maryland border.
The Philadelphia Electric Comp ...
, Unit 1
**
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 shu ...
**
Fort St. Vrain Generating Station
The Fort St. Vrain Nuclear Power Plant was a commercial nuclear power station located near the town of Platteville in northern Colorado in the United States. It operated from 1979 until 1989. It had a 330 MWe High-temperature gas reactor (HTGR) ...
*High temperature gas-cooled reactors (in development or construction)
**
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 des ...
**
Very high temperature reactor
A high-temperature gas-cooled reactor (HTGR), is a nuclear reactor that uses a graphite moderator with a once-through uranium fuel cycle. The HTGR is a type of high-temperature reactor (HTR) that can conceptually have an outlet temperature of ...
**
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 ...
**
UHTREX
The Ultra-High Temperature Reactor Experiment (UHTREX) was an experimental gas-cooled nuclear reactor run at Los Alamos National Laboratory between 1959 and 1971 Ultra-high-temperature reactor experiment
*Other
**
Molten salt reactor
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 molten salt mixture. Only two MSRs have ever operated, both research reactors in the United States. The 1950's ...
Research reactors
There have been a number of research or test reactors built that use graphite as the moderator.
*
Chicago Pile-1
*
Chicago Pile-2
*
Transient Reactor Test Facility
The Transient Reactor Test Facility (TREAT) is an air-cooled, graphite moderated, thermal spectrum test nuclear reactor designed to test reactor fuels and structural materials. Constructed in 1958, and operated from 1959 until 1994, TREAT was ...
(TREAT)
*
Molten Salt Reactor Experiment
The Molten-Salt Reactor Experiment (MSRE) was an experimental molten salt reactor research reactor at the Oak Ridge National Laboratory (ORNL). This technology was researched through the 1960s, the reactor was constructed by 1964, it went critic ...
(MSRE)
History
The first artificial nuclear reactor,
Chicago Pile-1, a graphite-moderated device that produced between 0.5 watts and 200 watts , was constructed by a team led by
Enrico Fermi in 1942. The construction and testing of this reactor (an "
atomic pile") was part of the
Manhattan Project
The Manhattan Project was a research and development undertaking during World War II that produced the first nuclear weapons. It was led by the United States with the support of the United Kingdom and Canada. From 1942 to 1946, the project w ...
. This work led to the construction of the
X-10 Graphite Reactor at
Oak Ridge National Laboratory
Oak Ridge National Laboratory (ORNL) is a U.S. multiprogram science and technology national laboratory sponsored by the U.S. Department of Energy (DOE) and administered, managed, and operated by UT–Battelle as a federally funded research an ...
, which was the first nuclear reactor designed and built for continuous operation, and began operation in 1943.
Accidents
There have been several major
accidents
An accident is an unintended, normally unwanted event that was not directly caused by humans. The term ''accident'' implies that nobody should be blamed, but the event may have been caused by unrecognized or unaddressed risks. Most researche ...
in graphite-moderated reactors, with the
Windscale fire
The Windscale fire of 10 October 1957 was the worst nuclear accident in the United Kingdom's history, and one of the worst in the world, ranked in severity at level 5 out of a possible 7 on the International Nuclear Event Scale. The fire was in ...
and the
Chernobyl disaster probably the best known.
In the Windscale fire, an untested annealing process for the graphite was used, and that contributed to the accident – however it was the uranium fuel rather than the graphite in the reactor that caught fire. The only graphite moderator damage was found to be localized around burning fuel elements.
In the Chernobyl disaster, the graphite was a contributing factor to the cause of the accident. Due to overheating from lack of adequate cooling, the fuel rods began to deteriorate. After the
SCRAM
A scram or SCRAM is an emergency shutdown of a nuclear reactor effected by immediately terminating the fission reaction. It is also the name that is given to the manually operated kill switch that initiates the shutdown. In commercial reactor ...
(AZ5) button was pressed to shut down the reactor, the control rods jammed in the middle of the core, causing a positive loop, since the nuclear fuel reacted to graphite. This has been dubbed the "final trigger" of events before the rupture. A graphite fire after the main event contributed to the spread of radioactive material. The massive power excursion in Chernobyl during a mishandled test led to the rupture of the reactor vessel and a series of steam explosions, which destroyed the reactor building. Now exposed to both air and the heat from the reactor core, the graphite moderator in the reactor core caught fire, and this fire sent a plume of highly radioactive fallout into the atmosphere and over an extensive geographical area.
In addition, the French
Saint-Laurent Nuclear Power Plant
The Saint-Laurent Nuclear Power Station is located in the commune of Saint-Laurent-Nouan in Loir-et-Cher on the Loire – 28 km upstream from Blois and 30 km downstream from Orléans.
The site includes two operating pressurized ...
and the Spanish
Vandellòs Nuclear Power Plant
The Vandellòs Nuclear Power Plant is a nuclear power plant in Vandellòs located close to the Coll de Balaguer pass (Baix Camp comarca) in Catalonia, Spain.
Unit one was a 508 MWe carbon dioxide gas cooled reactor modeled on the UNGG reactor ...
– both
UNGG
The UNGG (''Uranium Naturel Graphite Gaz'') is an obsolete nuclear power reactor design developed in France. It was graphite moderated, cooled by carbon dioxide, and fueled with natural uranium metal. The first generation of French nuclear ...
graphite-moderated
natural uranium reactors – suffered major accidents. Particularly noteworthy is a partial core meltdown on 17 October 1969 and a heat excursion during graphite annealing on 13 March 1980 in Saint-Laurent, which were both classified as
INES
Ines or INES may refer to:
People
* Ines (name), a feminine given name, also written as Inés or Inês
* Saint Ines or Agnes (), Roman virgin–martyr
* Eda-Ines Etti (stage name: ''Ines''; born 1981), Estonian singer
Places
* Doña Ines, a vo ...
4. The Vandellòs NPP was damaged on 19 October 1989, and a repair was considered uneconomical.
References
{{DEFAULTSORT:Graphite Moderated Reactor
Nuclear power reactor types