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undergraduate thesis
Ekstrakcija uranija(VI) i plutonija (IV) it otpadnog nuklearnog goriva
završni rad
2020. urn:nbn:hr:167:796535
Zenunović, Lidija
University of Split
Faculty of Chemistry and Technology
Division of Engineering and Chemistry

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Zenunović, L. (2020). Ekstrakcija uranija(VI) i plutonija (IV) it otpadnog nuklearnog goriva : završni rad (Undergraduate thesis). Split: University of Split, Faculty of Chemistry and Technology. Retrieved from https://urn.nsk.hr/urn:nbn:hr:167:796535

Zenunović, Lidija. "Ekstrakcija uranija(VI) i plutonija (IV) it otpadnog nuklearnog goriva : završni rad." Undergraduate thesis, University of Split, Faculty of Chemistry and Technology, 2020. https://urn.nsk.hr/urn:nbn:hr:167:796535

Zenunović, Lidija. "Ekstrakcija uranija(VI) i plutonija (IV) it otpadnog nuklearnog goriva : završni rad." Undergraduate thesis, University of Split, Faculty of Chemistry and Technology, 2020. https://urn.nsk.hr/urn:nbn:hr:167:796535

Zenunović, L. (2020). 'Ekstrakcija uranija(VI) i plutonija (IV) it otpadnog nuklearnog goriva : završni rad', Undergraduate thesis, University of Split, Faculty of Chemistry and Technology, accessed 26 April 2024, https://urn.nsk.hr/urn:nbn:hr:167:796535

Zenunović L. Ekstrakcija uranija(VI) i plutonija (IV) it otpadnog nuklearnog goriva : završni rad [Undergraduate thesis]. Split: University of Split, Faculty of Chemistry and Technology; 2020 [cited 2024 April 26] Available at: https://urn.nsk.hr/urn:nbn:hr:167:796535

L. Zenunović, "Ekstrakcija uranija(VI) i plutonija (IV) it otpadnog nuklearnog goriva : završni rad", Undergraduate thesis, University of Split, Faculty of Chemistry and Technology, Split, 2020. Available at: https://urn.nsk.hr/urn:nbn:hr:167:796535

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Metadata
TitleEkstrakcija uranija(VI) i plutonija (IV) it otpadnog nuklearnog goriva : završni rad
Title (english)Extraction of uranium(VI) and plutonium(IV) from a nuclear waste : bachelor thesis
AuthorLidija Zenunović
MentorBoris-Marko Kukovec (mentor)
Committee memberVesna Sokol (predsjednik povjerenstva)
Committee memberNives Vladislavić (član povjerenstva)
Committee memberBoris-Marko Kukovec (član povjerenstva)
GranterUniversity of Split
Faculty of Chemistry and Technology
(Division of Engineering and Chemistry)
Split
Defense date and country2020-09-28, Croatia
Scientific / art field,
discipline and subdiscipline		TECHNICAL SCIENCES
Chemical Engineering
Abstract
Ekstrakcija uranija i plutonija se izvodi primjenom PUREX procesa (engl. Plutonium Uranium Reduction Extraction). U radu su objašnjene današnje metode i varijacije PUREX procesa koje su najviše zastupljene. UtvrĎene su značajke PUREX procesa i optimalni načini provoĎenja istog, te istaknuta važnost oporabe otpadnog nuklearnog goriva. Plutonij(IV) i uranij(VI) tvore stabilne komplekse s nitratima i organskim ekstraktantom tri-n-butil fosfatom (TBP), a što omogućuje njihovo odvajanje od fisijskih produkata. Nastali neutralni kompleksi plutonija(IV) i uranija(VI) s nitratima i TBP-om se koekstrahiraju u organsku fazu (npr. kerozin) dok kationi fisijskih produkata uglavnom ne tvore komplekse s TBP-om i ne ekstrahiraju se. Nakon uklanjanja fisijskih produkata, plutonij(IV) i uranij(VI) se meĎusobno odvajaju na temelju selektivnog reduciranja Pu(IV) do Pu(III) koji se ne ekstrahira u opisanim uvjetima, te se zadržava u vodenoj fazi. Uranij(VI) se ne reducira i ekstrahira se u organsku fazu. Razdvojeni uranij(VI) i plutonij(IV) se dodatno pročišćavaju. Kljuĉne rijeĉi: ekstrakcija, uranij(VI), plutonij(IV), oporaba nuklearnog otpada
Abstract (english)
Extraction of uranium and plutonium is performed by the PUREX process (Plutonium Uranium Reduction Extraction). The thesis explains contemporary methods and variations of the PUREX process that have been studied and most commonly used. The characteristics of the PUREX process and the optimal ways of its implementation have been determined, and the importance of recovering a nuclear waste fuel has been emphasized. Plutonium(IV) and uranium(VI) form stable nitrate complexes with the organic extractant tri-n- butyl phosphate (TBP) that allows their separation from the fission products. The neutral plutonium(IV) and uranium(VI) complexes formed with nitrates and TBP are then coextracted into an organic phase (e. g. kerosene), while the cations of fission products generally do not form TBP complexes and do not extract. After a removal of the fission products, plutonium(IV) and uranium(VI) are separated from each other based on a selective reduction of Pu(IV) to Pu(III). Plutonium(III) does not extract and remains in the aqueous phase, while uranium(VI) is not reduced and is extracted into the organic phase under described conditions. The separated uranium(VI) and plutonium(IV) are additionally purified.
Keywords
Keywords (english)
Languagecroatian
URN:NBNurn:nbn:hr:167:796535
Study programmeTitle: Chemical Technology; specializations in: Chemical Engineering, Environmental Protection
Course: Chemical Engineering
Study programme type: university
Study level: undergraduate
Academic / professional title: sveučilišni/a prvostupnik/ prvostupnica (baccalaureus/baccalaurea) inženjer/inženjerka kemijskog inženjerstva (sveučilišni/a prvostupnik/ prvostupnica (baccalaureus/baccalaurea) inženjer/inženjerka kemijskog inženjerstva)
Type of resourceText
File originBorn digital
Access conditionsOpen access
Terms of useLicence In copyright icon
Created on2020-12-11 06:56:06