GB1362410A - Process for separating uranium and thorium from spent nuclear fuels - Google Patents
Process for separating uranium and thorium from spent nuclear fuelsInfo
- Publication number
- GB1362410A GB1362410A GB5437071A GB5437071A GB1362410A GB 1362410 A GB1362410 A GB 1362410A GB 5437071 A GB5437071 A GB 5437071A GB 5437071 A GB5437071 A GB 5437071A GB 1362410 A GB1362410 A GB 1362410A
- Authority
- GB
- United Kingdom
- Prior art keywords
- solution
- thorium
- uranium
- spent nuclear
- nitric acid
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired
Links
- ZSLUVFAKFWKJRC-IGMARMGPSA-N 232Th Chemical compound [232Th] ZSLUVFAKFWKJRC-IGMARMGPSA-N 0.000 title abstract 4
- 229910052776 Thorium Inorganic materials 0.000 title abstract 4
- 229910052770 Uranium Inorganic materials 0.000 title abstract 4
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 title abstract 3
- 239000003758 nuclear fuel Substances 0.000 title 1
- 239000000243 solution Substances 0.000 abstract 4
- KCXVZYZYPLLWCC-UHFFFAOYSA-N EDTA Chemical compound OC(=O)CN(CC(O)=O)CCN(CC(O)=O)CC(O)=O KCXVZYZYPLLWCC-UHFFFAOYSA-N 0.000 abstract 3
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 abstract 3
- 229960001484 edetic acid Drugs 0.000 abstract 3
- 229910017604 nitric acid Inorganic materials 0.000 abstract 3
- STCOOQWBFONSKY-UHFFFAOYSA-N tributyl phosphate Chemical compound CCCCOP(=O)(OCCCC)OCCCC STCOOQWBFONSKY-UHFFFAOYSA-N 0.000 abstract 3
- KVNYFPKFSJIPBJ-UHFFFAOYSA-N 1,2-diethylbenzene Chemical compound CCC1=CC=CC=C1CC KVNYFPKFSJIPBJ-UHFFFAOYSA-N 0.000 abstract 2
- SNRUBQQJIBEYMU-UHFFFAOYSA-N dodecane Chemical compound CCCCCCCCCCCC SNRUBQQJIBEYMU-UHFFFAOYSA-N 0.000 abstract 2
- 230000004992 fission Effects 0.000 abstract 2
- 150000003839 salts Chemical class 0.000 abstract 2
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract 2
- NTIZESTWPVYFNL-UHFFFAOYSA-N Methyl isobutyl ketone Chemical compound CC(C)CC(C)=O NTIZESTWPVYFNL-UHFFFAOYSA-N 0.000 abstract 1
- UIHCLUNTQKBZGK-UHFFFAOYSA-N Methyl isobutyl ketone Natural products CCC(C)C(C)=O UIHCLUNTQKBZGK-UHFFFAOYSA-N 0.000 abstract 1
- 229910002651 NO3 Inorganic materials 0.000 abstract 1
- NHNBFGGVMKEFGY-UHFFFAOYSA-N Nitrate Chemical compound [O-][N+]([O-])=O NHNBFGGVMKEFGY-UHFFFAOYSA-N 0.000 abstract 1
- VXLCKSFMONBCLQ-UHFFFAOYSA-N [Na]CC[Na] Chemical group [Na]CC[Na] VXLCKSFMONBCLQ-UHFFFAOYSA-N 0.000 abstract 1
- 239000007864 aqueous solution Substances 0.000 abstract 1
- 239000003795 chemical substances by application Substances 0.000 abstract 1
- 230000000536 complexating effect Effects 0.000 abstract 1
- LVHRUHVOYXWOMW-UHFFFAOYSA-N di(butan-2-yloxy)phosphorylbenzene Chemical compound CCC(C)OP(=O)(OC(C)CC)C1=CC=CC=C1 LVHRUHVOYXWOMW-UHFFFAOYSA-N 0.000 abstract 1
- RTZKZFJDLAIYFH-UHFFFAOYSA-N diethyl ether Substances CCOCC RTZKZFJDLAIYFH-UHFFFAOYSA-N 0.000 abstract 1
- 229940071106 ethylenediaminetetraacetate Drugs 0.000 abstract 1
- 239000012527 feed solution Substances 0.000 abstract 1
- 239000003350 kerosene Substances 0.000 abstract 1
- 229940043265 methyl isobutyl ketone Drugs 0.000 abstract 1
- 238000011084 recovery Methods 0.000 abstract 1
- 238000000926 separation method Methods 0.000 abstract 1
- -1 uranium carbides Chemical class 0.000 abstract 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
- G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
-
- 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)
- Extraction Or Liquid Replacement (AREA)
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE19702057760 DE2057760A1 (de) | 1970-11-24 | 1970-11-24 | Verfahren zur verbesserten Spaltproduktabtrennung bei der waessrigen Wiederaufarbeitung von abgebrannten Kernbrennstoffen |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1362410A true GB1362410A (en) | 1974-08-07 |
Family
ID=5788990
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB5437071A Expired GB1362410A (en) | 1970-11-24 | 1971-11-23 | Process for separating uranium and thorium from spent nuclear fuels |
Country Status (6)
| Country | Link |
|---|---|
| US (1) | US3836625A (enExample) |
| BE (1) | BE775757A (enExample) |
| DE (1) | DE2057760A1 (enExample) |
| FR (1) | FR2115372B1 (enExample) |
| GB (1) | GB1362410A (enExample) |
| IT (1) | IT943684B (enExample) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0348991A3 (en) * | 1988-07-01 | 1990-01-31 | Hitachi, Ltd. | Method for evaporation treatment of ruthenium-containing nitric acid solution and apparatus therefor |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2929167A1 (de) * | 1979-07-19 | 1981-02-05 | Uhde Gmbh | Verfahren zur reinigung der bei der wiederaufbereitung von bestrahlten kernbrennstoffen nach dem purex-prozess vorhandenen produktloesungen von tritium |
| FR2537326A1 (fr) * | 1982-12-01 | 1984-06-08 | Commissariat Energie Atomique | Procede de recuperation des actinides et/ou des lanthanides presents a l'etat trivalent dans une solution aqueuse acide |
| US4681705A (en) * | 1985-10-15 | 1987-07-21 | Carolina Power & Light Company | Decontamination of radioactively contaminated liquids |
| CN105467069A (zh) * | 2015-12-29 | 2016-04-06 | 中核北方核燃料元件有限公司 | 一种四氟化钍中钍含量的测定方法 |
-
1970
- 1970-11-24 DE DE19702057760 patent/DE2057760A1/de active Pending
-
1971
- 1971-11-22 US US20121671 patent/US3836625A/en not_active Expired - Lifetime
- 1971-11-22 IT IT3146971A patent/IT943684B/it active
- 1971-11-23 GB GB5437071A patent/GB1362410A/en not_active Expired
- 1971-11-24 BE BE775757A patent/BE775757A/xx unknown
- 1971-11-24 FR FR7142045A patent/FR2115372B1/fr not_active Expired
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0348991A3 (en) * | 1988-07-01 | 1990-01-31 | Hitachi, Ltd. | Method for evaporation treatment of ruthenium-containing nitric acid solution and apparatus therefor |
Also Published As
| Publication number | Publication date |
|---|---|
| US3836625A (en) | 1974-09-17 |
| BE775757A (fr) | 1972-05-24 |
| IT943684B (it) | 1973-04-10 |
| FR2115372A1 (enExample) | 1972-07-07 |
| DE2057760A1 (de) | 1972-05-25 |
| FR2115372B1 (enExample) | 1976-04-30 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PS | Patent sealed [section 19, patents act 1949] | ||
| PLNP | Patent lapsed through nonpayment of renewal fees |