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Enriched uranium
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==Grades== Uranium as it is taken directly from the Earth is not suitable as fuel for most nuclear reactors and requires additional processes to make it usable ([[CANDU]] design is a notable exception). Uranium is mined either underground or in an open pit depending on the depth at which it is found. After the [[uranium ore]] is mined, it must go through a milling process to extract the uranium from the ore. This is accomplished by a combination of chemical processes with the end product being concentrated uranium oxide, which is known as "[[yellowcake]]", contains roughly 80% uranium whereas the original ore typically contains as little as 0.1% uranium.<ref>[https://world-nuclear.org/information-library/nuclear-fuel-cycle/introduction/nuclear-fuel-cycle-overview.aspx Nuclear Fuel Cycle Overview], ''Uranium milling''. World Nuclear Association, update April 2021</ref> This yellowcake is further processed to obtain the desired form of uranium suitable for [[nuclear fuel]] production. After the milling process is complete, the uranium must next undergo a process of conversion, "to either [[uranium dioxide]], which can be used as the fuel for those types of reactors that do not require enriched uranium, or into [[uranium hexafluoride]], which can be enriched to produce fuel for the majority of types of reactors".<ref>{{cite web|url=https://www.hsdl.org/?view&did=770258 |title=Radiological Sources of Potential Exposure and/or Contamination |publisher=U.S. Army Center for Health Promotion and Preventive Medicine |page=27 |date=June 1999 |access-date=1 July 2019}}</ref> Naturally occurring uranium is made of a mixture of <sup>235</sup>U and <sup>238</sup>U. The <sup>235</sup>U is [[fissile]], meaning it is easily split with [[neutron]]s while the remainder is <sup>238</sup>U, but in nature, more than 99% of the extracted ore is <sup>238</sup>U. Most nuclear reactors require enriched uranium, which is uranium with higher concentrations of <sup>235</sup>U ranging between 3.5% and 4.5% (although a few reactor designs using a [[graphite]] or [[heavy water]] [[Neutron moderator|moderator]], such as the [[RBMK]] and [[CANDU]], are capable of operating with natural uranium as fuel). There are two commercial enrichment processes: [[gaseous diffusion]] and [[gas centrifugation]]. Both enrichment processes involve the use of uranium hexafluoride and produce enriched uranium oxide.<ref name="auto">{{Cite journal |last=Olander |first=Donald R. |date=1981-01-01 |title=The theory of uranium enrichment by the gas centrifuge |url=https://dx.doi.org/10.1016/0149-1970%2881%2990026-3 |journal=Progress in Nuclear Energy |volume=8 |issue=1 |pages=1–33 |doi=10.1016/0149-1970(81)90026-3 |issn=0149-1970}}</ref> [[File:LEUPowder.jpg|thumb|A drum of [[yellowcake]] (a mixture of uranium precipitates)]] ===Reprocessed uranium (RepU)=== {{Main|Reprocessed uranium}} Reprocessed uranium (RepU) undergoes a series of chemical and physical treatments to extract usable uranium from spent nuclear fuel. RepU is a product of [[nuclear fuel cycle]]s involving [[nuclear reprocessing]] of [[spent fuel]]. RepU recovered from [[light water reactor]] (LWR) spent fuel typically contains slightly more <sup>235</sup>U than [[natural uranium]], and therefore could be used to fuel reactors that customarily use natural uranium as fuel, such as [[CANDU reactor]]s. It also contains the undesirable isotope [[uranium-236]], which undergoes [[neutron capture]], wasting neutrons (and requiring higher <sup>235</sup>U enrichment) and creating [[neptunium-237]], which would be one of the more mobile and troublesome radionuclides in [[deep geological repository]] disposal of nuclear waste. Reprocessed uranium often carries traces of other transuranic elements and fission products, necessitating careful monitoring and management during fuel fabrication and reactor operation. ===Low-enriched uranium (LEU){{Anchor|Low-enriched uranium}}=== Low-enriched uranium (LEU) has a lower than 20% concentration of <sup>235</sup>U; for instance, in commercial LWR, the most prevalent power reactors in the world, uranium is enriched to 3 to 5% <sup>235</sup>U. {{anchor|SEU}}<!-- [[Slightly enriched uranium]] redirects here-->'''Slightly enriched uranium''' ('''SEU''') has a concentration of under 2% <sup>235</sup>U.<ref>{{cite journal |last1=Carter |first1=John P. |last2=Borrelli |first2=R.A. |title=Integral molten salt reactor neutron physics study using Monte Carlo N-particle code |journal=Nuclear Engineering and Design |date=August 2020 |volume=365 |pages=110718 |doi=10.1016/j.nucengdes.2020.110718 |s2cid=225435681 |doi-access=free }}</ref> ===High-assay LEU (HALEU)=== High-assay LEU (HALEU) is enriched between 5% and 20%<ref>{{Cite web|url=https://www.energy.gov/sites/prod/files/2019/04/f61/HALEU%20Report%20to%20NEAC%20Committee%203-28-19%20%28FINAL%29.pdf |archive-url=https://ghostarchive.org/archive/20221009/https://www.energy.gov/sites/prod/files/2019/04/f61/HALEU%20Report%20to%20NEAC%20Committee%203-28-19%20%28FINAL%29.pdf |archive-date=2022-10-09 |url-status=live|title=High-assay low enriched uranium|last=Herczeg|first=John W.|date=28 March 2019|website=energy.gov}}</ref> and is called for in many [[small modular reactor]] (SMR) designs.<ref name=nei-20240630>{{cite news |url=https://www.neimagazine.com/analysis/haleu-uf6-and-smr-fuel-fabrication/?cf-view |title=HALEU UF6 and SMR fuel fabrication |publisher=Nuclear Engineering International |date=30 June 2024 |access-date=16 July 2024}}</ref> Fresh LEU used in [[research reactor]]s is usually enriched between 12% and 19.75% <sup>235</sup>U; the latter concentration is used to replace HEU fuels when converting to LEU.<ref>{{cite conference |last=Glaser |first=Alexander |date=6 November 2005 |title=About the Enrichment Limit for Research Reactor Conversion : Why 20%? |url=http://www.princeton.edu/~aglaser/2005aglaser_why20percent.pdf |url-status=live |conference=The 27th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR |publisher=Princeton University |archive-url=https://ghostarchive.org/archive/20221009/http://www.princeton.edu/~aglaser/2005aglaser_why20percent.pdf |archive-date=2022-10-09 |access-date=18 April 2014}}</ref> ===Highly enriched uranium (HEU)=== [[File:HEUraniumC.jpg|thumb|A [[billet (bar stock)|billet]] of highly enriched uranium metal]] Highly enriched uranium (HEU) has a 20% or higher concentration of <sup>235</sup>U. This high enrichment level is essential for nuclear weapons and certain specialized reactor designs. The fissile uranium in [[nuclear weapon]] primaries usually contains 85% or more of <sup>235</sup>U known as [[weapons grade]], though theoretically for an [[nuclear weapon design|implosion design]], a minimum of 20% could be sufficient (called weapon-usable) although it would require hundreds of kilograms of material and "would not be practical to design";<ref name="DefWpnsUsable">{{cite web |url= http://web.ornl.gov/info/reports/1998/3445606060721.pdf |title= Definition of Weapons-Usable Uranium-233 |last1= Forsberg |first1= C. W. |last2= Hopper |first2= C. M. |last3= Richter |first3= J. L. |last4= Vantine |first4= H. C. |date= March 1998 |work= ORNL/TM-13517 |publisher= Oak Ridge National Laboratories |access-date= 30 October 2013 |url-status= dead |archive-url= https://web.archive.org/web/20131102011417/http://web.ornl.gov/info/reports/1998/3445606060721.pdf |archive-date= 2 November 2013}}</ref><ref name="NWFAQ">{{cite web |url= http://www.nuclearweaponarchive.org/Nwfaq/Nfaq4-1.html#Nfaq4.1.7.1 |title= Nuclear Weapons FAQ, Section 4.1.7.1: Nuclear Design Principles – Highly Enriched Uranium |last= Sublette |first= Carey |date= 4 October 1996 |work= Nuclear Weapons FAQ |access-date=2 October 2010}}</ref> even lower enrichment is hypothetically possible, but as the enrichment percentage decreases the [[Critical mass (nuclear)|critical mass]] for unmoderated [[fast neutron]]s rapidly increases, with for example, an [[infinity|infinite]] mass of 5.4% <sup>235</sup>U being required.<ref name="DefWpnsUsable"/> For [[Criticality (status)|criticality]] experiments, enrichment of uranium to over 97% has been accomplished.<ref>{{cite journal |last=Mosteller |first=R.D. |year=1994 |title=Detailed Reanalysis of a Benchmark Critical Experiment: Water-Reflected Enriched-Uranium Sphere |journal=Los Alamos Technical Paper |issue=LA–UR–93–4097 |page=2 |url=http://www.osti.gov/bridge/servlets/purl/10120434-rruwqp/native/10120434.PDF |archive-url=https://ghostarchive.org/archive/20221009/http://www.osti.gov/bridge/servlets/purl/10120434-rruwqp/native/10120434.PDF |archive-date=2022-10-09 |url-status=live |access-date=19 December 2007 |quote=The enrichment of the pin and of one of the hemispheres was 97.67 w/o, while the enrichment of the other hemisphere was 97.68 w/o.|doi=10.2172/10120434 }}</ref> The first uranium bomb, [[Little Boy]], dropped by the United States on [[Hiroshima]] in 1945, used {{Convert|64|kg}} of 80% enriched uranium. Wrapping the weapon's fissile core in a [[neutron reflector]] (which is standard on all nuclear explosives) can dramatically reduce the critical mass. Because the core was surrounded by a neutron reflector, at explosion it comprised almost 2.5 critical masses. Neutron reflectors, compressing the fissile core via implosion, [[fusion boosting]], and "tamping", which slows the expansion of the fissioning core with inertia, allow [[nuclear weapon design]]s that use less than what would be one bare-sphere critical mass at normal density. The presence of too much of the <sup>238</sup>U isotope inhibits the runaway [[nuclear chain reaction]] that is responsible for the weapon's power. The critical mass for 85% highly enriched uranium is about {{convert|50|kg}}, which at normal density would be a sphere about {{convert|17|cm}} in diameter.<ref name="auto"/> Later U.S. nuclear weapons usually use [[plutonium-239]] in the primary stage, but the jacket or tamper secondary stage, which is compressed by the primary nuclear explosion, often uses HEU with enrichment between 40% and 80%<ref>{{cite web|url=http://nuclearweaponarchive.org/Nwfaq/Nfaq6.html#nfaq6.2 |title=Nuclear Weapons FAQ |access-date=26 January 2013}}</ref> along with the [[nuclear fusion|fusion]] fuel [[lithium deuteride]]. This multi-stage design enhances the efficiency and effectiveness of nuclear weapons, allowing for greater control over the release of energy during detonation. For the secondary of a large nuclear weapon, the higher critical mass of less-enriched uranium can be an advantage as it allows the core at explosion time to contain a larger amount of fuel. This design strategy optimizes the explosive yield and performance of advanced nuclear weapons systems. The <sup>238</sup>U is not said to be fissile but still is fissionable by fast neutrons (>2 MeV) such as the ones produced during [[deuterium–tritium fusion|D–T fusion]].<ref name="Lei Science Direct">{{Cite journal |last1=Lei |first1=Jia |last2=Liu |first2=Huanhuan |last3=Zhou |first3=Li |last4=Wang |first4=Yazhou |last5=Yu |first5=Kaifu |last6=Zhu |first6=Hui |last7=Wang |first7=Bo |last8=Zang |first8=Mengxuan |last9=Zhou |first9=Jian |last10=He |first10=Rong |last11=Zhu |first11=Wenkun |date=2023-09-01 |title=Progress and perspective in enrichment and separation of radionuclide uranium by biomass functional materials |url=https://www.sciencedirect.com/science/article/pii/S138589472303317X |journal=Chemical Engineering Journal |volume=471 |pages=144586 |doi=10.1016/j.cej.2023.144586 |issn=1385-8947|url-access=subscription }}</ref> HEU is also used in [[fast neutron reactor]]s, whose cores require about 20% or more of fissile material, as well as in [[Nuclear marine propulsion|naval reactors]], where it often contains at least 50% <sup>235</sup>U, but typically does not exceed 90%. These specialized reactor systems rely on highly enriched uranium for their unique operational requirements, including high neutron flux and precise control over reactor dynamics. The [[Fermi 1|Fermi-1]] commercial fast reactor prototype used HEU with 26.5% <sup>235</sup>U. Significant quantities of HEU are used in the production of [[medical isotopes]], for example [[molybdenum-99]] for [[technetium-99m generator]]s.<ref>{{cite journal |last1=Von Hippel |first1=Frank N. |last2=Kahn |first2=Laura H. |date=December 2006 |title=Feasibility of Eliminating the Use of Highly Enriched Uranium in the Production of Medical Radioisotopes |journal=Science & Global Security |volume=14 |issue=2 & 3 |pages=151–162 |bibcode=2006S&GS...14..151V |doi=10.1080/08929880600993071 |s2cid=122507063}}</ref> The medical industry benefits from the unique properties of highly enriched uranium, which enable the efficient production of critical isotopes essential for diagnostic imaging and therapeutic applications.
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