Natural uranium reactor

from Wikipedia, the free encyclopedia

A natural uranium reactor is a nuclear reactor that works with natural, i.e. non- enriched uranium as a nuclear fuel .

Drawing of the Chicago Pile 1 , the first nuclear reactor to achieve criticality in 1942

use

The first experimental test reactors from the 1940s and 1950s, but also some commercial power reactors , especially in Great Britain , France , Canada and India , used natural uranium. In Germany , research reactor 2 , the Niederaichbach nuclear power plant and the Karlsruhe multi-purpose research reactor were operated with natural uranium. Today (2020) natural uranium is still used for energy production in around 50 reactors of the CANDU type.

Physical background

In natural uranium, the proportion of the easily fissile uranium isotope 235 U is around 0.7%. In a reactor with natural uranium fuel, criticality , i.e. a self-sustaining nuclear fission chain reaction , cannot be achieved with every, but only with certain moderator substances; With the most economical moderator and coolant, ordinary water (light water), it does not work because too many neutrons are lost through absorption. All natural uranium reactors are therefore either heavy water reactors or graphite-moderated reactors. Either pure uranium metal (U) or uranium dioxide (UO 2 ) is used as fuel .

Most of today's nuclear power plants use enriched uranium with a 235 U content of 0.7% to 2%, with some reactor types up to 20%. Highly enriched uranium (20% to 93% 235 U) is used in a few research reactors and in nuclear weapons .

In the Oklo natural reactor and other uranium deposits in Gabon , critical nuclear fission chain reactions with natural uranium took place around two billion years ago. At that time, the proportion of 235 U in natural uranium was around 3%, so that the criticality could arise even with moderation with normal water.

Commercial power reactors

The following nuclear power plants were or are operated with natural uranium. In the case of nuclear power plants with several units, the first unit is indicated under “Start of operation” and that of the last unit under “End of operation”, and that of the most powerful unit under “Output”.

Magnox reactors

Scheme of a Magnox reactor

Magnox reactors ( engl. Magnesium Alloy Graphite Moderated Gas Cooled Reactor Uranium oxides ) are graphite-moderated nuclear reactors with carbon dioxide (CO 2 to be cooled). The fuel elements consist of natural uranium in metallic form, which is coated with a magnesium - aluminum alloy.

Magnox reactors were developed in the UK and were among the first commercial nuclear reactors in the world. The design was implemented in 26 UK reactors and two nuclear power plants in Italy and Japan . Today there is no longer a Magnox reactor in operation; the last remaining reactor was shut down at the Wylfa nuclear power plant on December 30, 2015.

As a successor to the Magnox reactor, the Advanced Gas-cooled Reactor was developed in Great Britain in the 1960s, but it uses uranium dioxide enriched to around 3% as a nuclear fuel.

Surname country power operating
beginning
operating
end
Remarks
Calder Hall 1-4 Great Britain 50 MW Aug 1956 Mar 2003 First nuclear power plant used commercially to generate electricity, it was also used to generate plutonium
Chapelcross 1-4 Great Britain 50 MW Feb 1959 Jun 2004 was built and used parallel to Calder Hall
Berkeley 1-2 Great Britain 138 MW Jun 1962 Mar 1989 first nuclear power plant in the UK built for commercial use only
Bradwell 1-2 Great Britain 123 MW Jul 1962 Mar 2002
Latina Italy 153 MW May 1963 Dec 1987 was shut down in the train of Italy's nuclear phase-out
Hunterston A1-A2 Great Britain 150 MW Feb 1964 Mar 1990
Trawsfynydd 1-2 Great Britain 159 MW Jan 1965 Feb 1991
Hinkley Point A1-A2 Great Britain 235 MW Feb 1965 May 2000
Dungeness A1-A2 Great Britain 225 MW Sep 1965 Dec 2006
Tōkai Japan 159 MW Nov 1965 Mar 1998
Size wave A1-A2 Great Britain 210 MW Jan 1966 Dec 2006
Oldbury A1-A2 Great Britain 217 MW Nov 1967 Feb 2012
Wylfa 1-2 Great Britain 490 MW Jan 1971 Dec 2015

UNGG reactors

The UNGG reactors ( French Uranium Naturel Graphite Gaz ), which were developed in France in the 1950s and 1960s , were similar in design to the Magnox reactors and were moderated with graphite and cooled with carbon dioxide. The fuel elements in UNGG reactors were also made of natural uranium, but here they were coated with a magnesium- zirconium alloy. UNGG reactors were used in eight French nuclear reactors and in the Spanish nuclear power plant Vandellòs , none of the reactors is now in operation.

The UNGG design has been replaced in France by pressurized water reactors , all of which are operated with enriched uranium.

Surname country power operating
beginning
operating
end
Remarks
Marcoule G1-G3 France 40 MW Sep 1956 Jun 1984
Quinone A1-A3 France 360 MW Jun 1963 Jun 1990
Saint-Laurent A1-A2 France 515 MW Mar 1969 May 1992 Incident (INES 4)
Bugey 1 France 540 MW Apr 1972 May 1994
Vandellòs 1 Spain 480 MW May 1972 Jul 1990 was switched off permanently after a fire in October 1989

CANDU reactors

The Pickering nuclear power plant with eight CANDU reactors

See also: List of CANDU reactors

The CANDU reactor was developed in Canada . CANDU reactors use heavy water as a moderator and also (in a separate circuit with overpressure) as a coolant. Natural uranium or slightly enriched uranium can be used as nuclear fuel.

The reactor type is used in many countries, especially Canada, but also in Argentina , China , Pakistan , Romania and South Korea . 34 of the 36 CANDU reactors are still in operation today.

The Advanced CANDU Reactor is an evolution of the CANDU design, which uses slightly enriched uranium.

Surname country power operating
beginning
operating
end
Remarks
Rolphton Canada 22 MW Jun 1962 Aug 1987 Prototype for CANDU reactors
Douglas Point Canada 206 MW Jan 1967 May 1984 Canada's first commercially operated nuclear power plant
Pickering 1-8 Canada 516 MW Apr 1971
Gentilly 1-2 Canada 635 MW Apr 1971 Unit 1 was a prototype for the heavy boiling water reactor
Rajasthan 1 India 90 MW Nov 1972
Karachi Pakistan 125 MW Dec 1972
Bruce 1-8 Canada 822 MW Sep 1976
Wolsong 1-4 South Korea 685 MW Dec 1982
Point Lepreau Canada 635 MW Feb 1983
Embalse Argentina 600 MW Apr 1983
Darlington 1-4 Canada 878 MW Jan 1990
Cernavoda 1-2 Romania 650 MW Jul 1996 only nuclear power plant in Romania
Qinshan 3-1,3-2 China 650 MW Nov 2002

Further heavy water pressure reactors

Most nuclear reactors in India are heavy water-pressure reactors ( Engl. Pressurized Heavy Water Reactor ), which are operated with natural uranium and based on the CANDU design. All 16 reactors are still in operation.

The Niederaichbach nuclear power plant in Germany , a heavy water moderated pressure tube reactor with CO 2 gas cooling, and the multi-purpose research reactor Karlsruhe , a pressure tube reactor moderated and cooled with heavy water, were also operated with natural uranium . Both plants have now been shut down. The multi-purpose research reactor served as a prototype for the Argentine nuclear power plant Atucha 1, which is still in operation today and now uses slightly (0.85%) enriched uranium for reasons of efficiency.

The R3 reactor at Ågesta nuclear power plant in Sweden was a pressure vessel reactor developed as part of the so-called "Swedish Line", which aimed to achieve independence from abroad through the use of indigenous, non-enriched uranium fuel elements; the later Swedish nuclear power plants, however, were light water reactors operated with enriched uranium. Reactor A1 in the Czechoslovakian nuclear power plant Bohunice was a gas-cooled prototype pressure tube reactor that was developed jointly with Russia and also operated with natural uranium. These two reactors have now also been shut down.

Surname country power operating
beginning
operating
end
Remarks
Ågesta Sweden 10 MW May 1964 Jun 1974 first Swedish nuclear power plant
MZFR Karlsruhe Germany 52 MW Sep 1965 May 1984 was also used as a research reactor
Bohunice A1 Czechoslovakia 93 MW Dec 1972 May 1979 first Czechoslovak nuclear power plant
Niederaichbach Germany 100 MW Jan 1973 Jul 1974 was only in operation for 18 months
Atucha 1 Argentina 100 MW Mar 1974 today uses slightly (0.85%) enriched uranium
Rajasthan 2-6 India 202 MW Nov 1980
Madras 1-2 India 202 MW Jul 1983
Narora 1-2 India 202 MW Jul 1989
Kakrapar 1-2 India 202 MW Nov 1992
Kaiga 1-4 India 202 MW Dec 1999
Tarapur 3-4 India 490 MW Mar 2000

Experimental and research reactors

Examples of experimental and research reactors that were or are operated with natural uranium are:

Graphite-moderated reactors

Surname country power operating
beginning
operating
end
Remarks
Chicago Pile 1 United States 0.5 W Feb 1942 Mar 1943 first nuclear reactor in which a controlled critical nuclear chain reaction took place
Chicago Pile 2 United States 2 w Mar 1943 1954 The Chicago Pile 1 was rebuilt in the Red Gate Woods (first Argonne National Laboratory ) as Chicago Pile 2.
F-1 Russia 24 W. Dec 1946 was operated with natural uranium as well as with 2% enriched uranium
GLEEP Great Britain 50 W Aug 1947 Sep 1990 first nuclear reactor in Western Europe
BR-1 Belgium 4 MW May 1956
Marius France 400 W 1960 Apr 1983
BEPO Great Britain 6.5 MW 1962 1968
Cesar France 10 W Dec 1964 Aug 1977

Heavy water moderated reactors

Surname country power operating
beginning
operating
end
Remarks
Chicago Pile 3 United States 300 W May 1944 1954 first heavy water reactor
Haigerloch Germany - (Mar 1945) (Apr 1945) did not achieve any criticality
ZEEP Canada 10 W Sep 1945 Oct 1970 first operational nuclear reactor outside of the United States
NRX Canada 25 MW Jul 1947 Mar 1993 For several years the most powerful nuclear reactor in the world
ZOÉ France 0.1 MW Dec 1948 1974
EL-2 France 2 MW 1952 1965
R1 Sweden 0.6 MW Jul 1954 1970
Aquilon France 18 MW 1956 ?
NRU Canada 200 MW Nov 1957 was switched to highly enriched uranium in 1964 and to weakly enriched uranium in 1991
RB Serbia 0 W Apr 1958 was later switched to highly enriched uranium
CIRUS India 40 MW Jul 1960
ZED-2 Canada 200 W Sep 1960
Diorite Switzerland 30 MW Oct 1960 1977
FR 2 Germany 12 MW Mar 1961 Dec 1981 first nuclear reactor in Germany that was built according to its own concept; was switched to weakly enriched uranium in 1966
JRR-3 Japan 10 MW 1962 1983
ESSOR European Union 43 MW Mar 1967 Jun 1983 The location was Ispra , Italy
TRR Taiwan 40 MW Jan 1973 1988
Dhruva India 100 MW Aug 1985

Military nuclear facilities

The
Hanford B reactor

All of today's nuclear powers (USA, Russia, Great Britain, France and the People's Republic of China, as well as India, Pakistan, Israel and North Korea) initially used natural uranium reactors to produce weapons- grade plutonium . The infrastructure for the production of nuclear weapons was created in some large-scale nuclear programs (see e.g. Manhattan Project , Force de frappe , Soviet atomic bomb project , China’s first research station for nuclear weapons and North Korean nuclear weapons program ). The first of these reactors from the 1940s and 1950s have now been shut down.

In the following military nuclear facilities , natural uranium reactors were used to produce plutonium.

Surname country Number of
reactors
Total
output
operating
beginning
operating
end
Remarks
Hanford Site United States 3 750 MW Jun 1943 Jun 1965 The plutonium produced was used for the Fat Man atomic bomb , which was dropped on the Japanese city of Nagasaki on August 9, 1945 .
Mayak Russia 7th 63 MW Jun 1948 1990 On September 29, 1957, one of the three most serious nuclear accidents in history occurred there.
Sellafield Great Britain 2 360 MW Oct 1950 Oct 1957 The Pile No. 1 and Pile No. 2 reactors were shut down after the Windscale fire in October 1957.
Tomsk Russia 5 45 MW 1955 Jun 2008 One of the three reactors (ADE-5) was also used for electricity and district heating.
Marcoule France 3 80 MW Sep 1956 Jun 1984 The three reactors G1 to G3 (see above) also provided power.
Zheleznogorsk Russia 3 27 MW Aug 1958 Apr 2010 One of the three reactors (ADE-2) was also used for power and district heating.
Bhabha India 2 140 MW Jul 1960 The two reactors CIRUS and Dhruva (see above) are officially declared as research reactors.
Dimona Israel 1 24 MW 1964 With French help, it was constructed identically to the G1 reactor. The Israeli government has so far neither confirmed nor denied that this is a military facility for the production of plutonium.
Jiuquan China 1 250 MW Oct 1966 The reactor was built with Soviet help.
Nyŏngbyŏn North Korea 1 25 MW Aug 1985 The Experimental Power Reactor was built without British support based on the approved construction plans of the Magnox reactors of the Calder Hall nuclear power plant , it was also used to generate electricity (about 5 MWe).
Khushab Pakistan 1 50 MW Apr 1998 The reactor was developed independently, Saudi Arabia co-financed the project (see Saudi Arabia's nuclear program ).

See also

literature

Web links

supporting documents

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