PL97306B1 - METHOD OF SEPARATING TRANSURANCERS, ESPECIALLY PLUTOON FROM SPENT NUCLEAR FUEL - Google Patents
METHOD OF SEPARATING TRANSURANCERS, ESPECIALLY PLUTOON FROM SPENT NUCLEAR FUEL Download PDFInfo
- Publication number
- PL97306B1 PL97306B1 PL18879176A PL18879176A PL97306B1 PL 97306 B1 PL97306 B1 PL 97306B1 PL 18879176 A PL18879176 A PL 18879176A PL 18879176 A PL18879176 A PL 18879176A PL 97306 B1 PL97306 B1 PL 97306B1
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- Poland
- Prior art keywords
- solution
- nuclear fuel
- spent nuclear
- minutes
- separating
- Prior art date
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- 238000000034 method Methods 0.000 title claims description 9
- 239000002915 spent fuel radioactive waste Substances 0.000 title claims description 9
- 229910052778 Plutonium Inorganic materials 0.000 claims description 7
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 claims description 7
- 230000003647 oxidation Effects 0.000 claims description 5
- 238000007254 oxidation reaction Methods 0.000 claims description 5
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 claims description 3
- CBENFWSGALASAD-UHFFFAOYSA-N Ozone Chemical compound [O-][O+]=O CBENFWSGALASAD-UHFFFAOYSA-N 0.000 claims description 3
- 229910052770 Uranium Inorganic materials 0.000 claims description 3
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims description 3
- 239000000203 mixture Substances 0.000 claims description 3
- 229910017604 nitric acid Inorganic materials 0.000 claims description 3
- 229910052760 oxygen Inorganic materials 0.000 claims description 3
- 239000001301 oxygen Substances 0.000 claims description 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims description 3
- 238000003776 cleavage reaction Methods 0.000 claims 1
- 238000004090 dissolution Methods 0.000 claims 1
- 230000007017 scission Effects 0.000 claims 1
- 239000013049 sediment Substances 0.000 claims 1
- 230000004992 fission Effects 0.000 description 3
- 239000000047 product Substances 0.000 description 3
- 238000000926 separation method Methods 0.000 description 3
- 238000000605 extraction Methods 0.000 description 2
- 239000002244 precipitate Substances 0.000 description 2
- 229910052781 Neptunium Inorganic materials 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 150000002500 ions Chemical class 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- LFNLGNPSGWYGGD-UHFFFAOYSA-N neptunium atom Chemical compound [Np] LFNLGNPSGWYGGD-UHFFFAOYSA-N 0.000 description 1
- 239000002901 radioactive waste Substances 0.000 description 1
- 238000003608 radiolysis reaction Methods 0.000 description 1
- 230000008929 regeneration Effects 0.000 description 1
- 238000011069 regeneration method Methods 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 229910052713 technetium Inorganic materials 0.000 description 1
- GKLVYJBZJHMRIY-UHFFFAOYSA-N technetium atom Chemical compound [Tc] GKLVYJBZJHMRIY-UHFFFAOYSA-N 0.000 description 1
Landscapes
- Inorganic Compounds Of Heavy Metals (AREA)
Description
Przedmiotem wynalazku jest sposób wydzielania transuranowców, zwlaszcza plutonu z wypalonego paliwa jadrowego, który moze byc wykorzystywany w produkcji materialów rozszczepialnych.Znany stan techniki. Obszerna literatura swiatowa dotyczaca regeneracji wypalonego paliwa jadrowego podaje wiele sposobów wydzielania i separacji róznych produktów rozszczepienia. Wedlug F.S. Martina i J.L.Milesa — „Chimiczeskaja piererabotka jadernowo topliwa" Izd. Innostr. Literat. Moskwa 1961 sposób wydziele¬ nia transuranowców polega na rozpuszczeniu wypalonego paliwa w kwasie azotowym. Uzyskany roztwór filtruje sie a nastepnie poddaje sie wielostopniowej ekstrakcji. Nieznane sa dotychczas sposoby polegajace na zastosowa¬ niu metod straceniowych w celu wstepnego rozdzielenia skladników zawartych w roztworze wypalonego paliwa jadrowego.Istota wynalazku. Wedlug wynalazku roztwór uzyskany przez rozpuszczenie wypalonego paliwa jadrowego w kwasie azotowym poddaje sie dzialaniu mieszaniny ozonu z tlenem i po okolo 30 minutach nie przerywajac utleniania powoli alkalizuje sie roztwór do pH okolo 10. Po uplywie okolo 30 minut podwyzsza sie pH roztworu do 12—13 i nadal utlenia sie roztwór przez 15—20 minut. Wytracony osad zawierajacy uran i produkty rozszczepienia oddziela sie od roztworu zawierajacego pluton.Korzystne skutki techniczne wynalazku. Sposób wedlug wynalazku w porównaniu ze sposobami wykorzys¬ tujacymi metody ekstrakcji odznacza sie prostota operacji i jest mniej czasochlonny. Eliminuje operowanie znacznymi objetosciami wysoce aktywnych roztworów, a odpady radioaktywne otrzymuje sie w stanie stalym.Zalete sposobu wedlug wynalazku stanowi równiez fakt, ze stosowane roztwory jedynie w minimalnym stopniu ulegaja procesom radiolizy, a prowadzenie procesu w srodowisku alkalicznym jest korzystne ze wzgledu na znacznie mniejsza korozje aparatury.Przyklad wykonania wynalazku. Wydzielenie plutonu z wypalonego paliwa jadrowego. Wypalone paliwo jadrowe rozpuszcza sie w 3MHN03. Przez roztwór przepuszcza sie mieszanine ozonu z tlenem w ciagu 25 minut.Nie przerywajac utleniania stopniowo przez 25 minut dodaje sie do roztworu 2,5 M KOH do osiagniecia pH = 10. Nastepnie równiez za pomoca KOH podwyzsza sie pH roztworu do 12,5 i prowadzi sie koncowe utlenianie jeszcze przez 15 minut.2 97 306 Wytracony osad zawierajacy uran wraz z produktami rozszczepienia odsacza sie a przesacz, w którym znajduje sie pluton w,postaci jonów PuOj~3, neptun jako Np05~3 oraz sladowe ilosci technetu w postaci TC04~ poddaje sie próbce znanymi sposobami w celu wydzielenia czystego plutonu. PLThe subject of the invention is a method of separating transuranides, especially plutonium from spent nuclear fuel, which can be used in the production of fissile materials. Prior art. The extensive world literature on spent nuclear fuel regeneration gives many methods for the separation and separation of various fission products. According to F.S. Martin and JLMiles - "Chimicheskaya piererabotka, edible melt" Izd. Innostr. Literat. Moscow 1961 the method of separating transuranides consists in dissolving the spent fuel in nitric acid. The obtained solution is filtered and then subjected to multi-stage extraction. SUMMARY OF THE INVENTION According to the invention, the solution obtained by dissolving the spent nuclear fuel in nitric acid is subjected to the action of a mixture of ozone and oxygen, and after about 30 minutes without interrupting the oxidation, it slowly becomes alkaline. solution to a pH of about 10. After about 30 minutes, the pH of the solution is raised to 12-13 and the solution is still oxidized for 15-20 minutes. The precipitate containing uranium and fission products is separated from the solution containing plutonium. Advantageous technical effects of the invention. according to the invention in comp When used with extraction methods, the operation is simple and less time-consuming. It eliminates the handling of large volumes of highly active solutions, and the radioactive waste is obtained in a solid state. The advantage of the method according to the invention is also the fact that the solutions used are only minimally subject to radiolysis processes, and carrying out the process in an alkaline environment is advantageous due to the much lower corrosion apparatus. An embodiment of the invention. Separation of plutonium from spent nuclear fuel. The spent nuclear fuel dissolves in 3MHN03. A mixture of ozone and oxygen is passed through the solution for 25 minutes. Without stopping the oxidation, 2.5 M KOH is gradually added to the solution for 25 minutes until the pH is 10. Then the pH of the solution is also increased to 12.5 with KOH and carried out. final oxidation continues for 15 minutes. 2 97 306 The precipitate containing uranium with fission products is filtered off and the effluent containing plutonium in the form of PuOj ~ 3 ions, neptunium as Np05 ~ 3 and trace amounts of technetium in the form of TC04 ~ the sample is subjected to known methods in order to isolate pure plutonium. PL
Claims (1)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| PL18879176A PL97306B1 (en) | 1976-04-14 | 1976-04-14 | METHOD OF SEPARATING TRANSURANCERS, ESPECIALLY PLUTOON FROM SPENT NUCLEAR FUEL |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| PL18879176A PL97306B1 (en) | 1976-04-14 | 1976-04-14 | METHOD OF SEPARATING TRANSURANCERS, ESPECIALLY PLUTOON FROM SPENT NUCLEAR FUEL |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| PL97306B1 true PL97306B1 (en) | 1978-02-28 |
Family
ID=19976424
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| PL18879176A PL97306B1 (en) | 1976-04-14 | 1976-04-14 | METHOD OF SEPARATING TRANSURANCERS, ESPECIALLY PLUTOON FROM SPENT NUCLEAR FUEL |
Country Status (1)
| Country | Link |
|---|---|
| PL (1) | PL97306B1 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0049827A1 (en) * | 1980-10-14 | 1982-04-21 | Alkem Gmbh | Process for the dissolving of hard soluble plutonium oxide |
-
1976
- 1976-04-14 PL PL18879176A patent/PL97306B1/en unknown
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0049827A1 (en) * | 1980-10-14 | 1982-04-21 | Alkem Gmbh | Process for the dissolving of hard soluble plutonium oxide |
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