Uranium enrichment - Revision history

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energy>Luisa at 19:48, 17 October 2021

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	[[Category:Translated to French]]		[[Category:Translated to French]]
	[[fr:Enrichissement de l'uranium]]		[[fr:Enrichissement de l'uranium]]
			[[Category:Translated to Spanish]]
			[[es:Enriquecimiento del uranio]]
	[[File:Uraninite-usa32abg.jpg\|300px\|thumb\|right\|Figure 1. A form of uranium ore known as Uraninite.<ref>Wikimedia Commons. (May 5, 2016). ''Uraninite'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Uraninite-usa32abg.jpg</ref>]]		[[File:Uraninite-usa32abg.jpg\|300px\|thumb\|right\|Figure 1. A form of uranium ore known as Uraninite.<ref>Wikimedia Commons. (May 5, 2016). ''Uraninite'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Uraninite-usa32abg.jpg</ref>]]

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	===Gas Centrifuges===		===Gas Centrifuges===
	:''[[Gas centrifuge for uranium enrichment\|main article]]''		:''[[Gas centrifuge for uranium enrichment\|main article]]''
	[[File:600px-Gas_centrifuge_cascade.jpg\|400px\|framed\|right\|Figure 2. Cascade of centrifuges used to produce enriched uranium.<ref>Wikimedia Commons. (June 17, 2015). ''Gas Centrifuge Cascade'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Gas_centrifuge_cascade.jpg#/media/File:Gas_centrifuge_cascade.jpg</ref>]]		[[File:600px-Gas_centrifuge_cascade.jpg\|400px\|framed\|right\|Figure 3. Cascade of centrifuges used to produce enriched uranium.<ref>Wikimedia Commons. (June 17, 2015). ''Gas Centrifuge Cascade'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Gas_centrifuge_cascade.jpg#/media/File:Gas_centrifuge_cascade.jpg</ref>]]
	Today, enrichment is achieved using a special [[centrifuge]] called a '''gas centrifuge'''. The separation process here relies on the [[mass]] difference of the molecules (see gaseous diffusion above). Here, uranium hexafluoride is fed into an evacuated cylinder containing a [[rotor]]. When these rotors are spun at a high [[speed]], the heavier <sup>238</sup>UF<sub>6</sub> collects near the walls of the cylinder while the slightly lighter <sup>235</sup>UF<sub>6</sub> collects near the central axis. The enriched product is then drawn off. This method is preferred over gaseous diffusion as it requires only about 3% of the power to separate the uranium.<ref name="RE1"/> A centrifugal separation method is much more energy-efficient than diffusion, as it requires only about 50-60 [[kWh]] per [[SWU]] (separative work unit, which is the amount of separation done by an enrichment process).<ref name="RE3"/> Additionally, these plants can be smaller as they don't require an extremely long pipe. For efficient separation to occur, these centrifuges must rotate quickly - generally at 50 000-70 000 [[rpm]].<ref name="RE2">Ian Hore-Lacy. (June 17, 2015). ''Nuclear Energy in the 12st Century'', 1st Ed. Burlington, MA, U.S.A: Elsevier Inc, 2006.</ref>		Today, enrichment is achieved using a special [[centrifuge]] called a '''gas centrifuge'''. The separation process here relies on the [[mass]] difference of the molecules (see gaseous diffusion above). Here, uranium hexafluoride is fed into an evacuated cylinder containing a [[rotor]]. When these rotors are spun at a high [[speed]], the heavier <sup>238</sup>UF<sub>6</sub> collects near the walls of the cylinder while the slightly lighter <sup>235</sup>UF<sub>6</sub> collects near the central axis. The enriched product is then drawn off. This method is preferred over gaseous diffusion as it requires only about 3% of the power to separate the uranium.<ref name="RE1"/> A centrifugal separation method is much more energy-efficient than diffusion, as it requires only about 50-60 [[kWh]] per [[SWU]] (separative work unit, which is the amount of separation done by an enrichment process).<ref name="RE3"/> Additionally, these plants can be smaller as they don't require an extremely long pipe. For efficient separation to occur, these centrifuges must rotate quickly - generally at 50 000-70 000 [[rpm]].<ref name="RE2">Ian Hore-Lacy. (June 17, 2015). ''Nuclear Energy in the 12st Century'', 1st Ed. Burlington, MA, U.S.A: Elsevier Inc, 2006.</ref>

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energy>Ethan.boechler at 17:26, 18 June 2021

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	[[Category:Done 2019-09-05]]		[[Category:Done 2019-09-05]]
			[[Category:Translated to French]]
			[[fr:Enrichissement de l'uranium]]
	[[File:Uraninite-usa32abg.jpg\|300px\|thumb\|right\|Figure 1. A form of uranium ore known as Uraninite.<ref>Wikimedia Commons. (May 5, 2016). ''Uraninite'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Uraninite-usa32abg.jpg</ref>]]		[[File:Uraninite-usa32abg.jpg\|300px\|thumb\|right\|Figure 1. A form of uranium ore known as Uraninite.<ref>Wikimedia Commons. (May 5, 2016). ''Uraninite'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Uraninite-usa32abg.jpg</ref>]]

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energy>Jmdonev at 19:53, 4 September 2019

2019-09-04T19:53:26Z

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	[[Category:Done ~~2017~~-07-01]]		[[Category:Done 2019-09-05]]
	[[File:Uraninite-usa32abg.jpg\|300px\|thumb\|right\|Figure 1. A form of uranium ore known as Uraninite.<ref>Wikimedia Commons. (May 5, 2016). ''Uraninite'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Uraninite-usa32abg.jpg</ref>]]		[[File:Uraninite-usa32abg.jpg\|300px\|thumb\|right\|Figure 1. A form of uranium ore known as Uraninite.<ref>Wikimedia Commons. (May 5, 2016). ''Uraninite'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Uraninite-usa32abg.jpg</ref>]]

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	===Gaseous Diffusion===		===Gaseous Diffusion===
	:''[[Gaseous diffusion\|main article]]''		:''[[Gaseous diffusion uranium enrichment\|main article]]''
	For many years the main process was '''gaseous diffusion'''. In order to physically separate the uranium the [[yellowcake]] uranium was first chemically transformed into uranium hexafluoride (UF<sub>6</sub>). This chemical is in its [[solid]] form under normal conditions, but transforms into a gas if the [[temperature]] is raised slightly or the [[pressure]] is lowered.<ref name="RE1"/> Since the <sup>235</sup>UF<sub>6</sub> [[molecule]]s are slightly lighter than the <sup>238</sup>UF<sub>6</sub> molecules, they move more quickly as a gas through [[Diffusion\|diffusion]]. Thus if uranium hexafluoride is passed through a very long pipe, the gas that emerges at the far end of the pipe will have a slightly higher percentage of <sup>235</sup>U. However, the pipe must be extremely long as the lighter <sup>235</sup>UF<sub>6</sub> diffuses only 0.43% faster than <sup>238</sup>UF<sub>6</sub>.<ref name="RE1"/> Because of this, the method of gaseous diffusion is not widely used anymore.		For many years the main process was '''gaseous diffusion'''. In order to physically separate the uranium the [[yellowcake]] uranium was first chemically transformed into uranium hexafluoride (UF<sub>6</sub>). This chemical is in its [[solid]] form under normal conditions, but transforms into a gas if the [[temperature]] is raised slightly or the [[pressure]] is lowered.<ref name="RE1"/> Since the <sup>235</sup>UF<sub>6</sub> [[molecule]]s are slightly lighter than the <sup>238</sup>UF<sub>6</sub> molecules, they move more quickly as a gas through [[Diffusion\|diffusion]]. Thus if uranium hexafluoride is passed through a very long pipe, the gas that emerges at the far end of the pipe will have a slightly higher percentage of <sup>235</sup>U. However, the pipe must be extremely long as the lighter <sup>235</sup>UF<sub>6</sub> diffuses only 0.43% faster than <sup>238</sup>UF<sub>6</sub>.<ref name="RE1"/> Because of this, the method of gaseous diffusion is not widely used anymore.

	===Gas Centrifuges===		===Gas Centrifuges===
	:''[[Gas centrifuge\|main article]]''		:''[[Gas centrifuge for uranium enrichment\|main article]]''
	[[File:600px-Gas_centrifuge_cascade.jpg\|400px\|framed\|right\|Figure 2. Cascade of centrifuges used to produce enriched uranium.<ref>Wikimedia Commons. (June 17, 2015). ''Gas Centrifuge Cascade'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Gas_centrifuge_cascade.jpg#/media/File:Gas_centrifuge_cascade.jpg</ref>]]		[[File:600px-Gas_centrifuge_cascade.jpg\|400px\|framed\|right\|Figure 2. Cascade of centrifuges used to produce enriched uranium.<ref>Wikimedia Commons. (June 17, 2015). ''Gas Centrifuge Cascade'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Gas_centrifuge_cascade.jpg#/media/File:Gas_centrifuge_cascade.jpg</ref>]]
	Today, enrichment is achieved using a special [[centrifuge]] called a '''gas centrifuge'''. The separation process here relies on the [[mass]] difference of the molecules (see gaseous diffusion above). Here, uranium hexafluoride is fed into an evacuated cylinder containing a [[rotor]]. When these rotors are spun at a high [[speed]], the heavier <sup>238</sup>UF<sub>6</sub> collects near the walls of the cylinder while the slightly lighter <sup>235</sup>UF<sub>6</sub> collects near the central axis. The enriched product is then drawn off. This method is preferred over gaseous diffusion as it requires only about 3% of the power to separate the uranium.<ref name="RE1"/> A centrifugal separation method is much more energy-efficient than diffusion, as it requires only about 50-60 [[kWh]] per [[SWU]] (separative work unit, which is the amount of separation done by an enrichment process).<ref name="RE3"/> Additionally, these plants can be smaller as they don't require an extremely long pipe. For efficient separation to occur, these centrifuges must rotate quickly - generally at 50 000-70 000 [[rpm]].<ref name="RE2">Ian Hore-Lacy. (June 17, 2015). ''Nuclear Energy in the 12st Century'', 1st Ed. Burlington, MA, U.S.A: Elsevier Inc, 2006.</ref>		Today, enrichment is achieved using a special [[centrifuge]] called a '''gas centrifuge'''. The separation process here relies on the [[mass]] difference of the molecules (see gaseous diffusion above). Here, uranium hexafluoride is fed into an evacuated cylinder containing a [[rotor]]. When these rotors are spun at a high [[speed]], the heavier <sup>238</sup>UF<sub>6</sub> collects near the walls of the cylinder while the slightly lighter <sup>235</sup>UF<sub>6</sub> collects near the central axis. The enriched product is then drawn off. This method is preferred over gaseous diffusion as it requires only about 3% of the power to separate the uranium.<ref name="RE1"/> A centrifugal separation method is much more energy-efficient than diffusion, as it requires only about 50-60 [[kWh]] per [[SWU]] (separative work unit, which is the amount of separation done by an enrichment process).<ref name="RE3"/> Additionally, these plants can be smaller as they don't require an extremely long pipe. For efficient separation to occur, these centrifuges must rotate quickly - generally at 50 000-70 000 [[rpm]].<ref name="RE2">Ian Hore-Lacy. (June 17, 2015). ''Nuclear Energy in the 12st Century'', 1st Ed. Burlington, MA, U.S.A: Elsevier Inc, 2006.</ref>

Jmdonev: 1 revision imported

2017-08-29T01:47:18Z

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Jmdonev at 19:08, 15 August 2017

2017-08-15T19:08:10Z

← Older revision		Revision as of 19:08, 15 August 2017
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	[[Category:Done ~~2016~~-04-30]]		[[Category:Done 2017-07-01]]
	[[File:Uraninite-usa32abg.jpg\|300px\|thumb\|right\|Figure 1. A form of uranium ore known as Uraninite.<ref>Wikimedia Commons. (May 5, 2016). ''Uraninite'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Uraninite-usa32abg.jpg</ref>]]		[[File:Uraninite-usa32abg.jpg\|300px\|thumb\|right\|Figure 1. A form of uranium ore known as Uraninite.<ref>Wikimedia Commons. (May 5, 2016). ''Uraninite'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Uraninite-usa32abg.jpg</ref>]]

	<onlyinclude>'''Uranium enrichment''' is a process that is necessary to create an effective [[nuclear fuel]] out of mined [[uranium]] by increasing the percentage of uranium-235 which undergoes [[fission]] with thermal [[neutron]]s.</onlyinclude> Although many reactors require enriched fuel, the Canadian-designed [[CANDU]], the British Magnox reactor and the proposed [[Molten salt reactor]] can use [[Grades of uranium enrichment\|natural uranium]] as their fuel.<ref name="RE3"/>		<onlyinclude>'''Uranium enrichment''' is a process that is necessary to create an effective [[nuclear fuel]] out of mined [[uranium]] by increasing the percentage of uranium-235 which undergoes [[fission]] with thermal [[neutron]]s.</onlyinclude> Although many reactors require [[Grades of uranium enrichment\|enriched uranium fuel]], the Canadian-designed [[CANDU]], the British [[Magnox reactor]] and the proposed [[Molten salt reactor]] can use [[Grades of uranium enrichment\|natural uranium]] as their [[fuel]].<ref name="RE3"/>

	Nuclear fuel is [[uranium mining\|mined]] from naturally occurring uranium [[ore]] deposits, and then isolated through [[chemical]] reactions and separation processes. These chemical processes used to separate the uranium from the ore are not to be confused with the physical and chemical processes used to enrich the uranium. In its isolated form, the uranium is known as [[yellowcake]] and has the chemical formula U<sub>3</sub>O<sub>8</sub>. However, naturally occurring uranium does not have a high enough concentration of <sup>235</sup>U at only about 0.72% with the remainder being <sup>238</sup>U.<ref name="RE1">Jeff C. Bryan. (June 17, 2015). ''Introduction to Nuclear Science'', 1st ed. Boca Raton, FL, U.S.A: CRC Press, 2009.</ref> Due to the fact that uranium-238 is [[Fissionable\|fissionable]] and not [[Fissile\|fissile]], the concentration of uranium-235 must be increased before it can be effectively used as a nuclear fuel. The purpose of uranium enrichment is to increase the percentage of the uranium-235 isotope with respect to others, with a necessary percentage of around 4% for [[~~Light~~ water~~, heavy water, and supercritical water nuclear~~ reactor~~\|light water reactors~~]].<ref name="RE1"/>		Nuclear fuel is [[uranium mining\|mined]] from naturally occurring uranium [[ore]] deposits, and then isolated through [[chemical]] reactions and separation processes. These chemical processes used to separate the uranium from the ore are not to be confused with the physical and chemical processes used to enrich the uranium. In its isolated form, the uranium is known as [[yellowcake]] and has the chemical formula U<sub>3</sub>O<sub>8</sub>. However, naturally occurring uranium does not have a high enough concentration of <sup>235</sup>U at only about 0.72% with the remainder being <sup>238</sup>U.<ref name="RE1">Jeff C. Bryan. (June 17, 2015). ''Introduction to Nuclear Science'', 1st ed. Boca Raton, FL, U.S.A: CRC Press, 2009.</ref> Due to the fact that uranium-238 is [[Fissionable\|fissionable]] and not [[Fissile\|fissile]], the concentration of uranium-235 must be increased before it can be effectively used as a nuclear fuel. The purpose of uranium enrichment is to increase the percentage of the uranium-235 isotope with respect to others, with a necessary percentage of around 4% for [[light water reactor]]s.<ref name="RE1"/>

	==Enrichment Processes==		==Enrichment Processes==
	[[File:Uranium-hexafluoride-3D-vdW.png\|300px\|thumb\|right\|Figure 2. The blue atom in the centre of the molecule is uranium, surrounded by six fluorine atoms. This substance becomes a gas at fairly low [[temperature]]s.]]		[[File:Uranium-hexafluoride-3D-vdW.png\|300px\|thumb\|right\|Figure 2. The blue atom in the centre of the molecule is uranium, surrounded by six fluorine atoms. This substance becomes a [[gas]] at fairly low [[temperature]]s.]]
	Enrichment requires uranium to be in a [[gas\|gaseous]] form, and the simplest way to achieve this is to convert it to a different chemical known as [[uranium hexafluoride]]. Uranium needs to be in a gaseous form for enrichment due to the varying chemical and physical properties the different isotopes (U-235 and U-238) have. These differences are most easily utilized and manipulated when uranium is in gaseous form.		Enrichment requires uranium to be in a [[gas\|gaseous]] form, and the simplest way to achieve this is to convert it to a different chemical known as [[uranium hexafluoride]]. Uranium needs to be in a gaseous form for enrichment due to the varying chemical and physical properties the different isotopes (U-235 and U-238) have. These differences are most easily utilized and manipulated when uranium is in gaseous form.

	The process of changing uranium oxide concentrate to uranium hexafluoride takes place at a conversion plant, the first step for uranium after it leaves a mine. The main conversion process used in Canada, France and Russia is known as the 'wet process' and involves multiple chemical conversion stages. Firstly, the uranium oxide concentrate is dissolved in nitric acid (HNO<sub>3</sub>), which creates uranyl nitrate (UO<sub>2</sub>(NO<sub>3</sub>)<sub>2</sub>). This uranyl nitrate is then purified, evaporated and finally thermally decomposed to form uranium trioxide powder (UO<sub>3</sub>). After which there are two kiln processes wherein the UO<sub>3</sub> is converted to UO<sub>2</sub>, then reacted with hydrogen fluoride (HF), to produce uranium tetrafluoride (UF<sub>4</sub>). Finally the UF<sub>4</sub> is fed into a [[~~Fluidised bed reactor\|~~fluidized bed reactor]] and reacted with gaseous fluorine to produce UF<sub>6</sub>. After the conversion process, the UF<sub>6</sub> needs to be further refined due to the presence of impurities.<ref name="RE5">World Nuclear Association. (May 12, 2016). ''Conversion and Deconversion''[Online]. Available: http://www.world-nuclear.org/information-library/nuclear-fuel-cycle/conversion-enrichment-and-fabrication/conversion-and-deconversion.aspx</ref>		The process of changing uranium oxide concentrate to uranium hexafluoride takes place at a conversion plant, the first step for uranium after it leaves a mine. The main conversion process used in Canada, France and Russia is known as the 'wet process' and involves multiple chemical conversion stages. Firstly, the uranium oxide concentrate is dissolved in nitric acid (HNO<sub>3</sub>), which creates uranyl nitrate (UO<sub>2</sub>(NO<sub>3</sub>)<sub>2</sub>). This uranyl nitrate is then purified, evaporated and finally thermally decomposed to form uranium trioxide powder (UO<sub>3</sub>). After which there are two kiln processes wherein the UO<sub>3</sub> is converted to UO<sub>2</sub>, then reacted with hydrogen fluoride (HF), to produce uranium tetrafluoride (UF<sub>4</sub>). Finally the UF<sub>4</sub> is fed into a [[fluidized bed reactor]] and reacted with gaseous fluorine to produce UF<sub>6</sub>. After the conversion process, the UF<sub>6</sub> needs to be further refined due to the presence of impurities.<ref name="RE5">World Nuclear Association. (May 12, 2016). ''Conversion and Deconversion''[Online]. Available: http://www.world-nuclear.org/information-library/nuclear-fuel-cycle/conversion-enrichment-and-fabrication/conversion-and-deconversion.aspx</ref>

	===Gaseous Diffusion===		===Gaseous Diffusion===
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	===Gas Centrifuges===		===Gas Centrifuges===
	:''[[~~Gaseous~~ centrifuge\|main article]]''		:''[[Gas centrifuge\|main article]]''
	[[File:600px-Gas_centrifuge_cascade.jpg\|400px\|framed\|right\|Figure 2. Cascade of centrifuges used to produce enriched uranium.<ref>Wikimedia Commons. (June 17, 2015). ''Gas Centrifuge Cascade'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Gas_centrifuge_cascade.jpg#/media/File:Gas_centrifuge_cascade.jpg</ref>]]		[[File:600px-Gas_centrifuge_cascade.jpg\|400px\|framed\|right\|Figure 2. Cascade of centrifuges used to produce enriched uranium.<ref>Wikimedia Commons. (June 17, 2015). ''Gas Centrifuge Cascade'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Gas_centrifuge_cascade.jpg#/media/File:Gas_centrifuge_cascade.jpg</ref>]]
	Today, enrichment is achieved using a '''gas centrifuge'''. The separation process here relies on the [[mass]] difference of the molecules (see gaseous diffusion above). Here, uranium hexafluoride is fed into an evacuated cylinder containing a [[rotor]]. When these rotors are spun at a high speed, the heavier <sup>238</sup>UF<sub>6</sub> collects near the walls of the cylinder while the slightly lighter <sup>235</sup>UF<sub>6</sub> collects near the central axis. The enriched product is then drawn off. This method is preferred over gaseous diffusion as it requires only about 3% of the power to separate the uranium.<ref name="RE1"/> A centrifugal separation method is much more energy-efficient than diffusion, as it requires only about 50-60 [[kWh]] per [[SWU]] (separative work unit, which is the amount of separation done by an enrichment process).<ref name="RE3"/> Additionally, these plants can be smaller as they don't require an extremely long pipe. For efficient separation to occur, these centrifuges must rotate quickly - generally at 50 000-70 000 [[rpm]].<ref name="RE2">Ian Hore-Lacy. (June 17, 2015). ''Nuclear Energy in the 12st Century'', 1st Ed. Burlington, MA, U.S.A: Elsevier Inc, 2006.</ref>		Today, enrichment is achieved using a special [[centrifuge]] called a '''gas centrifuge'''. The separation process here relies on the [[mass]] difference of the molecules (see gaseous diffusion above). Here, uranium hexafluoride is fed into an evacuated cylinder containing a [[rotor]]. When these rotors are spun at a high [[speed]], the heavier <sup>238</sup>UF<sub>6</sub> collects near the walls of the cylinder while the slightly lighter <sup>235</sup>UF<sub>6</sub> collects near the central axis. The enriched product is then drawn off. This method is preferred over gaseous diffusion as it requires only about 3% of the power to separate the uranium.<ref name="RE1"/> A centrifugal separation method is much more energy-efficient than diffusion, as it requires only about 50-60 [[kWh]] per [[SWU]] (separative work unit, which is the amount of separation done by an enrichment process).<ref name="RE3"/> Additionally, these plants can be smaller as they don't require an extremely long pipe. For efficient separation to occur, these centrifuges must rotate quickly - generally at 50 000-70 000 [[rpm]].<ref name="RE2">Ian Hore-Lacy. (June 17, 2015). ''Nuclear Energy in the 12st Century'', 1st Ed. Burlington, MA, U.S.A: Elsevier Inc, 2006.</ref>

	Although centrifuges hold less uranium than a diffusion stage, they are able to separate isotopes much more efficiently. Centrifuge stages generally are composed of a large number of centrifuges in parallel, forming a [[cascade process\|cascade]].		Although centrifuges hold less uranium than a diffusion stage, they are able to separate isotopes much more efficiently. Centrifuge stages generally are composed of a large number of centrifuges in parallel, forming a [[cascade process\|cascade]].
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	===Laser Isotope Separation===		===Laser Isotope Separation===
	:''[[Laser isotope separation\|main article]]''		:''[[Laser isotope separation\|main article]]''
	The use of lasers in a separation process is still being developed. This separation technique requires lower energy input and other economic advantages. In this process, a laser with a very specific frequency interacts with a gas or vapour. Since the frequency has an associated energy, the interaction of the beam with the gas allows for the excitation or [[ionization]] of certain isotopes in the vapour. With this excitement, it may be possible to separate molecules containing a specific isotope to collect only the excited isotope.<ref name="RE2"/>		The use of lasers in a separation process is still being developed. This separation technique requires lower [[energy]] input and other economic advantages. In this process, a laser with a very specific [[frequency]] interacts with a gas or vapour. Since the frequency has an associated energy, the interaction of the beam with the gas allows for the excitation or [[ionization]] of certain isotopes in the vapour. With this excitement, it may be possible to separate molecules containing a specific isotope to collect only the excited isotope.<ref name="RE2"/>

	==Environmental Issues==		==Environmental Issues==
	Most enrichment processes involve only natural, long-lived [[radioactivity\|radioactive]] materials. Uranium is only weakly radioactive, but its chemical toxicity is much more significant . Thus protective measures required for an enrichment plant are similar to those in other chemical industries. When exposed to moisture, uranium hexafluoride forms a very corrosive [[acid]], hydrofluoric acid. Any leakage of this chemical is undesirable and to prevent this almost all areas of an enrichment plant keep the uranium hexafluoride gas below [[atmospheric pressure]].<ref name="RE3">World Nuclear Association. (June 17, 2015). ''Uranium Enrichment'' [Online]. Available: http://www.world-nuclear.org/info/Nuclear-Fuel-Cycle/Conversion-Enrichment-and-Fabrication/Uranium-Enrichment/</ref> This stops any outward leakage. Additionally, double containment is provided in areas where higher pressures are required and venting gases are collected and treated.		Most enrichment processes involve only natural, long-lived [[radioactivity\|radioactive]] materials. Uranium is only weakly radioactive, but its chemical toxicity is much more significant . Thus protective measures required for an enrichment plant are similar to those in other chemical industries. When exposed to moisture, uranium hexafluoride forms a very corrosive [[acid]], hydrofluoric acid. Any leakage of this chemical is undesirable and to prevent this almost all areas of an enrichment plant keep the uranium hexafluoride gas below [[atmospheric pressure]].<ref name="RE3">World Nuclear Association. (June 17, 2015). ''Uranium Enrichment'' [Online]. Available: http://www.world-nuclear.org/info/Nuclear-Fuel-Cycle/Conversion-Enrichment-and-Fabrication/Uranium-Enrichment/</ref> This stops any outward leakage. Additionally, double containment is provided in areas where higher pressures are required and venting gases are collected and treated.

	Enrichment accounts for around half of the [[cost]] of nuclear fuel in a light water reactor (a [[BWR]] or [[PWR]]) and 5% of the cost of the electricity generated. Previously enrichment has been the main source of [[greenhouse gases]] from the nuclear fuel cycle as [[electricity]] used for enrichment was generated using [[coal]]. Although there are associated greenhouse gas [[emission]]s, it is only about 0.1% of the emissions of an equivalent [[coal-fired power plant]].<ref name="RE3"/>		Enrichment accounts for around half of the [[cost]] of nuclear fuel in a [[light water reactor]] (a [[BWR]] or [[PWR]]) and 5% of the cost of the electricity generated. Previously enrichment has been the main source of [[greenhouse gases]] from the [[nuclear fuel cycle]] as [[electricity]] used for enrichment was generated using [[coal]]. Although there are associated greenhouse gas [[emission]]s, it is only about 0.1% of the emissions of an equivalent [[coal-fired power plant]].<ref name="RE3"/>

	==References==		==References==
	{{reflist}}		{{reflist}}
	[[Category:Uploaded]]		[[Category:Uploaded]]

Jmdonev at 01:16, 18 September 2016

2016-09-18T01:16:05Z

← Older revision		Revision as of 01:16, 18 September 2016
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	[[Category:Done 2016-04-30]]		[[Category:Done 2016-04-30]]
	[[File:Uraninite-usa32abg ~~(1)~~.jpg\|300px\|thumb\|right\|Figure 1. A form of uranium ore known as Uraninite.<ref>Wikimedia Commons. (May 5, 2016). ''Uraninite'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Uraninite-usa32abg.jpg</ref>]]		[[File:Uraninite-usa32abg.jpg\|300px\|thumb\|right\|Figure 1. A form of uranium ore known as Uraninite.<ref>Wikimedia Commons. (May 5, 2016). ''Uraninite'' [Online]. Available: https://commons.wikimedia.org/wiki/File:Uraninite-usa32abg.jpg</ref>]]

	<onlyinclude>'''Uranium enrichment''' is a process that is necessary to create an effective [[nuclear fuel]] out of mined [[uranium]] by increasing the percentage of uranium-235 which undergoes [[fission]] with thermal [[neutron]]s.</onlyinclude> Although many reactors require enriched fuel, the Canadian-designed [[CANDU]], the British Magnox reactor and the proposed [[Molten salt reactor]] can use [[Grades of uranium enrichment\|natural uranium]] as their fuel.<ref name="RE3"/>		<onlyinclude>'''Uranium enrichment''' is a process that is necessary to create an effective [[nuclear fuel]] out of mined [[uranium]] by increasing the percentage of uranium-235 which undergoes [[fission]] with thermal [[neutron]]s.</onlyinclude> Although many reactors require enriched fuel, the Canadian-designed [[CANDU]], the British Magnox reactor and the proposed [[Molten salt reactor]] can use [[Grades of uranium enrichment\|natural uranium]] as their fuel.<ref name="RE3"/>

Jmdonev: 1 revision imported: From the summer

2016-09-17T22:29:38Z

1 revision imported: From the summer

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