LU83452A1 - METHOD FOR REPROCESSING IRRADIATED NUCLEAR FUELS - Google Patents
METHOD FOR REPROCESSING IRRADIATED NUCLEAR FUELS Download PDFInfo
- Publication number
- LU83452A1 LU83452A1 LU83452A LU83452A LU83452A1 LU 83452 A1 LU83452 A1 LU 83452A1 LU 83452 A LU83452 A LU 83452A LU 83452 A LU83452 A LU 83452A LU 83452 A1 LU83452 A1 LU 83452A1
- Authority
- LU
- Luxembourg
- Prior art keywords
- nuclear fuels
- irradiated nuclear
- reprocessing irradiated
- reprocessing
- plutonium
- Prior art date
Links
- 238000000034 method Methods 0.000 title claims description 7
- 238000012958 reprocessing Methods 0.000 title description 3
- 239000003758 nuclear fuel Substances 0.000 title description 2
- 229910052778 Plutonium Inorganic materials 0.000 description 6
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 5
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 3
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 description 3
- 229910017604 nitric acid Inorganic materials 0.000 description 3
- 238000006243 chemical reaction Methods 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 230000001590 oxidative effect Effects 0.000 description 2
- 239000000047 product Substances 0.000 description 2
- ZLMJMSJWJFRBEC-UHFFFAOYSA-N Potassium Chemical compound [K] ZLMJMSJWJFRBEC-UHFFFAOYSA-N 0.000 description 1
- BQCADISMDOOEFD-UHFFFAOYSA-N Silver Chemical compound [Ag] BQCADISMDOOEFD-UHFFFAOYSA-N 0.000 description 1
- 229910001854 alkali hydroxide Inorganic materials 0.000 description 1
- 150000008044 alkali metal hydroxides Chemical class 0.000 description 1
- 239000007795 chemical reaction product Substances 0.000 description 1
- 238000003776 cleavage reaction Methods 0.000 description 1
- 230000029087 digestion Effects 0.000 description 1
- 239000003337 fertilizer Substances 0.000 description 1
- 229910052700 potassium Inorganic materials 0.000 description 1
- 239000011591 potassium Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 238000009419 refurbishment Methods 0.000 description 1
- 230000007017 scission Effects 0.000 description 1
- 229910052709 silver Inorganic materials 0.000 description 1
- 239000004332 silver Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 230000001988 toxicity Effects 0.000 description 1
- 231100000419 toxicity Toxicity 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
- G21C19/48—Non-aqueous processes
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Processing Of Solid Wastes (AREA)
Description
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i ϊ : ι « $ . « SJROPAEISGHE AT0K3SMLIKSCHAFT' .i ϊ: ι «$. "SJROPAEISGHE AT0K3SMLIKSCHAFT '.
____________' ' ^JRATOK )____________ '' ^ JRATOK)
Patentanmei düngPatent anmei
Verfahr er zur Wi ederaufberei tune- i .......... """"' " —-SiL he strahlten j! Kernbrennstof Per, \ ! Erfinder: L. KOCH, R. LS MEEdT'ER llv,,If he goes to the refurbishment tune- i .......... "" "" '"—-SiL he beamed j! Nuclear fuel, \! Inventor: L. KOCH, R. LS MEEdT'ER llv, ,
- uriti \l. CO QUERELLE- uriti \ l. CO QUERELLE
i [ 1 - ; !| Bei der Wiederaufarbeitung von plutoniumhalx-j ;| m Brennstoffen nach dem ; bekannten PÜRSX-Verfahren fallen unlösliche j»,·· .i [1 -; ! | When reprocessing plutoniumhalx-j; | m fuels after; known PÜRSX processes fall insoluble j », ··.
'uCiisxändfe an, die unter- ardei-'uCiisxändfe, the subordinate
Plutonium enthalten. Entsorechend den Eerste'n · ~ &IContain plutonium. Desecrating the Eerste'n · ~ & I
! * 'χsoealnnrngec des Brenn- ; stoffes und den Bestrahlunfrsbedingungen könner — T... · ,.! * 'χsoealnnrngec des Brenn-; substance and the radiation conditions can - T ... ·,.
; - aie RucKsxande bis zu einige I Prozente des eingesetzter· Plutoniums betragen.; - aie RucKsxande up to a few I percent of the plutonium used.
Die Rückstände sind hochradioaktiv und senr refahrlieh und müssen unbedingt in lösliche Form gebracht und weiterverarbeitet -werden.The residues are highly radioactive and extremely mobile and must be brought into soluble form and processed.
!!
JJ
i , ç ! 1 ’ i r, I £_ ·"» i i Me Erfindung- besteht nun darin, die trockenen, nicht in Salpetersäure ! oder anderer, starken 3ä.ureri löslichen Rückstände, die bei der ersten Stufe des PURIX-Verfahrens enfallen, mit trockenen Alkalihydroxiden unter oxidierenden Bedingungen bei erhöhter Temperatur zu behandeln.i, ç! 1 'ir, I £ _ · "» ii Me invention- consists now in the dry, not in nitric acid! Or other strong 3ä.ureri residues, which are eliminated in the first stage of the PURIX process, with dry alkali hydroxides treat oxidizing conditions at elevated temperature.
Vorzugsweise erhitzt man den trockenen Rückstand im Mol-Verhältnis 1:4 innigst mit bei 12G°C getrocknetem KaOK vermischt und in GO,.-freier und trocnener Luft oder einem äquivalenter., oxidierenden Gasstrom ca 12 Stunden ' ' zwischen 550 - 600°C.The dry residue is preferably heated intimately in a molar ratio of 1: 4 mixed with KaOK dried at 12 ° C and in GO, - free and dry air or an equivalent, oxidizing gas stream for approx. 12 hours '' between 550 - 600 ° C .
Dabei wird unter anderem das Pu, enthalten in den in Salpetersäure unlöslich« Rückständen, in das ternäre Oxid der Brutxoformel Ka-PuO- übergeführt. Bei ; D C- ! der. Reaktionsfcedirgurgen bilden sich cum Teil auch löslicr.e ternäre Oxide !.. der Spaltprodukte# Der Umsatz zu der entsprechenden Amer iciumverb in düng ist unvollkommen, da bei dieser. Temperaturen die höherwertiger; ternären Americiui I oxide nicht mehr stabil sind.Among other things, the pu contained in the residues insoluble in nitric acid is converted into the ternary oxide of the brutal formula Ka-PuO-. At; D C-! the. Reaction process gurgen form cum part also soluble ternary oxides! .. of the cleavage products # The conversion to the corresponding Amer iciumverb in fertilizer is imperfect, because with this. Temperatures the higher quality; ternary Americiui I oxide are no longer stable.
t I Es wurden mehrere Versuche nach dem ober, beschriebener. Verfahren ausgeführt.t I There were several attempts after the one described above. Procedure executed.
Von den 270 mg im Rückstand vor. 1100 rg vorliegenden PuC·^. sind mindestensOf the 270 mg in arrears before. 1100 rg present PuC ^. are at least
; sL; sL
| 99/1 aufgelöst worden. (Da noch ungelöstes AmO.. vorlag, waren 3 mg die bacr.- \ weisgrenze für Pu.) Bei einem angenommener. Rückstand des PuCv von 2p beaeute* ? £ | ein Aufschluss von 99> des Rückstandes, dass dem, Wiedergewinnungspro zess S1“1·' des Plutoniums zugeführt werden kann.| 99/1 has been dissolved. (Since there was still undissolved AmO .., 3 mg was the bacr.- \ white limit for Pu.) For an assumed one. PuCv behind 2p *? £ | a digestion of 99> of the residue that can be added to the 'S1' 1 · 'recovery process of the plutonium.
Es sei erwähnt, dass das Reaktionsprodukt in 3 - 6 molarer HKO^ (entsprechen; . den Anforderungen der PUREX-Peed-Lösung) aufgelöst werden kann. Die zusätz- I liehe Zufuhr an KaliO^ in den Prozess wird in der Grössenordnung des ohnehin vorhandenen KaHQ- liegen.It should be mentioned that the reaction product can be dissolved in 3 - 6 molar HKO ^ (correspond to the requirements of the PUREX-Peed solution). The additional supply of potassium in the process will be of the order of magnitude of the KaHQ already present.
Beim Verfahren gemäss der Erfindung werden wie erwähnt die Plutoniumverluste bei der Wiederaufarbeitung reduziert. Dadurch wird nicht nur die Oekonomie des Pu-Zyklus verbessert, sondern auch die Toxizität des Abfalls verringert. Kostspielige Herstellungsverfahren, die zu einer Vervielfachung des Herstellungspreises plutoniumhaltiger Brennstoffe führen, können vermieden werden.In the process according to the invention, as mentioned, the plutonium losses during reprocessing are reduced. This not only improves the economy of the Pu cycle, but also reduces the toxicity of the waste. Costly manufacturing processes that lead to a multiplication of the manufacturing price of fuels containing plutonium can be avoided.
1/2010 _ 3 _ » 3eisoiel1/2010 _ 3 _ »3eisoiel
Es uarden 1100 mg Rückstand mit 270 mg PuG„ und 7 mg AmO^ in einem Behälter aus Silber gemäss der 3rfindüng mit NaOH 12 Stunden auf cOO°C erhitzt.1100 mg of residue were heated with 270 mg of PuG "and 7 mg of AmO ^ in a container made of silver according to the 3rfindüng with NaOH to cOO ° C for 12 hours.
Bas erhaltene Product wurde in Salpetersäure gelöst und filtriert. Im ! Rückstand waren im Filter Pu und Am nicht mehr messbar.The product obtained was dissolved in nitric acid and filtered. In the ! Residues were no longer measurable in the Pu and Am filters.
Ί | I *' ! ί si ! Μ Ί .1 J 1/2010 - L· -Ί | I * '! ί si! Μ Ί .1 J 1/2010 - L · -
Claims (1)
Priority Applications (6)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| LU83452A LU83452A1 (en) | 1981-06-24 | 1981-06-24 | METHOD FOR REPROCESSING IRRADIATED NUCLEAR FUELS |
| DE3221688A DE3221688A1 (en) | 1981-06-24 | 1982-06-04 | METHOD FOR REPROCESSING IRRADIATED FUELS |
| GB8216895A GB2105096B (en) | 1981-06-24 | 1982-06-10 | Process for the reprocessing of irradiated nuclear fuels |
| BE1/10530A BE893514A (en) | 1981-06-24 | 1982-06-15 | PROCESS FOR RE-TREATMENT OF IRRADIATED FUELS |
| IT4869282A IT1148342B (en) | 1981-06-24 | 1982-06-23 | PROCEDURE FOR RE-TREATMENT OF RADIATED NUCLEAR FUELS |
| FR8211092A FR2508692B1 (en) | 1981-06-24 | 1982-06-24 | PROCESS FOR THE RE-TREATMENT OF IRRADIATED FUELS |
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| LU83452A LU83452A1 (en) | 1981-06-24 | 1981-06-24 | METHOD FOR REPROCESSING IRRADIATED NUCLEAR FUELS |
| LU83452 | 1981-06-24 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| LU83452A1 true LU83452A1 (en) | 1981-10-29 |
Family
ID=19729677
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| LU83452A LU83452A1 (en) | 1981-06-24 | 1981-06-24 | METHOD FOR REPROCESSING IRRADIATED NUCLEAR FUELS |
Country Status (6)
| Country | Link |
|---|---|
| BE (1) | BE893514A (en) |
| DE (1) | DE3221688A1 (en) |
| FR (1) | FR2508692B1 (en) |
| GB (1) | GB2105096B (en) |
| IT (1) | IT1148342B (en) |
| LU (1) | LU83452A1 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE102010036737A1 (en) * | 2010-07-29 | 2012-02-02 | Erwin Krüger | Process for the dry reprocessing of spent nuclear fuel (irradiated) and an apparatus for carrying out the process |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE1199748B (en) * | 1963-05-15 | 1965-09-02 | Kernforschung Mit Beschraenkte | Process for processing irradiated nuclear fuel |
| DE1467322B2 (en) * | 1964-06-10 | 1972-06-22 | Europäische Atomgemeinschaft (EURATOM), Brüssel | PROCESS FOR THE RECYCLING OF OXYDIC NUCLEAR REACTOR FUEL |
| FR1483117A (en) * | 1965-06-10 | 1967-06-02 | Kernforschungsanlage Juelich | Process for the preparation of coated nuclear fuels |
-
1981
- 1981-06-24 LU LU83452A patent/LU83452A1/en unknown
-
1982
- 1982-06-04 DE DE3221688A patent/DE3221688A1/en not_active Withdrawn
- 1982-06-10 GB GB8216895A patent/GB2105096B/en not_active Expired
- 1982-06-15 BE BE1/10530A patent/BE893514A/en not_active IP Right Cessation
- 1982-06-23 IT IT4869282A patent/IT1148342B/en active
- 1982-06-24 FR FR8211092A patent/FR2508692B1/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| DE3221688A1 (en) | 1983-01-13 |
| IT8248692A0 (en) | 1982-06-23 |
| FR2508692A1 (en) | 1982-12-31 |
| GB2105096A (en) | 1983-03-16 |
| IT1148342B (en) | 1986-12-03 |
| FR2508692B1 (en) | 1988-08-05 |
| GB2105096B (en) | 1985-10-09 |
| BE893514A (en) | 1982-10-01 |
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