Editing Nuclear reprocessing (section)

=====UNEX=====
The '''''UN'''iversal'' '''EX'''traction process was developed in Russia and the [[Czech Republic]]; it is designed to completely remove the most troublesome [[radioisotopes]] (Sr, Cs and [[minor actinides]]) from the raffinate remaining after the extraction of uranium and plutonium from used [[nuclear fuel]].<ref>{{cite web |url=http://www.usembassy.it/file2001_12/alia/a1121910.htm |archive-url=https://web.archive.org/web/20140728001906/http://www.usembassy.it/file2001_12/alia/a1121910.htm |archive-date=28 July 2014 | title=U.S.-Russia Team Makes Treating Nuclear Waste Easier |publisher=U.S. embassy press release(?) | date=19 December 2001 |access-date=14 June 2007}}</ref><ref>{{cite web |url=http://www.osti.gov/bridge/product.biblio.jsp?osti_id=765723 |title=INTEC High-Level Waste Studies Universal Solvent Extraction Feasibility Study |publisher=INEEL Technical report |date=1 September 2001 |author=J. Banaee |display-authors=etal |access-date=28 January 2006 |archive-date=13 May 2013 |archive-url=https://web.archive.org/web/20130513122509/http://www.osti.gov/bridge/product.biblio.jsp?osti_id=765723 |url-status=live }}</ref> The chemistry is based upon the interaction of [[caesium]] and [[strontium]] with [[polyethylene glycol]]<ref>{{cite journal|doi=10.1081/SEI-100001371|title=The Universal Solvent Extraction (Unex) Process. Ii. Flowsheet Development and Demonstration of the Unex Process for the Separation of Cesium, Strontium, and Actinides from Actual Acidic Radioactive Waste|year=2001|last1=Law|first1=Jack D.|last2=Herbst|first2=R. Scott|last3=Todd|first3=Terry A.|last4=Romanovskiy|first4=Valeriy N.|last5=Babain|first5=Vasily A.|last6=Esimantovskiy|first6=Vyatcheslav M.|last7=Smirnov|first7=Igor V.|last8=Zaitsev|first8=Boris N.|journal=Solvent Extraction and Ion Exchange|volume=19|page=23|s2cid=98103735}}</ref><ref>{{cite journal|doi=10.1081/SEI-100001370|title=The Universal Solvent Extraction (Unex) Process. I. Development of the Unex Process Solvent for the Separation of Cesium, Strontium, and the Actinides from Acidic Radioactive Waste|year=2001|last1=Romanovskiy|first1=Valeriy N.|last2=Smirnov|first2=Igor V.|last3=Babain|first3=Vasily A.|last4=Todd|first4=Terry A.|last5=Herbst|first5=R. Scott|last6=Law|first6=Jack D.|last7=Brewer|first7=Ken N.|journal=Solvent Extraction and Ion Exchange|volume=19|page=1|s2cid=98166395}}</ref> and a [[cobalt]] [[carborane]] [[anion]] (known as chlorinated cobalt dicarbollide). The actinides are extracted by CMPO, and the [[diluent]] is a polar [[aromatic]] such as [[nitrobenzene]]. Other diluents such as ''meta''-nitrobenzotri[[fluoride]]<ref>{{Cite conference |last=Smirnov |first=Igor |date=2–6 March 2014 |title=UNEX-T Solvent for Cs, Sr and Actinides Separation from PUREX Raffinate – 14154 |url=https://archivedproceedings.econference.io/wmsym/2014/papers/14154.pdf |conference=Waste Management Symposium |via=econference.io}}</ref> and phenyl trifluoromethyl [[sulfone]]<ref>{{cite web| url=http://www.wmsym.org/Abstracts/2001/62/62-7.pdf | archive-url=https://web.archive.org/web/20070928141036/http://www.wmsym.org/Abstracts/2001/62/62-7.pdf | archive-date=28 September 2007 | title=Flowsheet testing of the universal solvent extraction process for the simultaneous separation of caesium, strontium, and the actinides from dissolved INEEL calcine |author=J.D. Law| publisher=WM 2001 conference proceedings| date=1 March 2001|access-date=17 June 2006|display-authors=etal}}</ref> have been suggested as well.