FR2376499A1 - Procede d'extraction de produits de fission contenus dans des elements combustibles nucleaires irradies - Google Patents
Procede d'extraction de produits de fission contenus dans des elements combustibles nucleaires irradiesInfo
- Publication number
- FR2376499A1 FR2376499A1 FR7639569A FR7639569A FR2376499A1 FR 2376499 A1 FR2376499 A1 FR 2376499A1 FR 7639569 A FR7639569 A FR 7639569A FR 7639569 A FR7639569 A FR 7639569A FR 2376499 A1 FR2376499 A1 FR 2376499A1
- Authority
- FR
- France
- Prior art keywords
- prods
- soln
- fuel elements
- pref
- water
- 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.)
- Granted
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title abstract 4
- 229910052740 iodine Inorganic materials 0.000 title abstract 3
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 title abstract 2
- 230000004992 fission Effects 0.000 title abstract 2
- 239000011630 iodine Substances 0.000 title abstract 2
- 239000003758 nuclear fuel Substances 0.000 title abstract 2
- 230000002285 radioactive effect Effects 0.000 title abstract 2
- 238000002386 leaching Methods 0.000 title 1
- 239000000446 fuel Substances 0.000 abstract 5
- 229910052792 caesium Inorganic materials 0.000 abstract 2
- XTVVROIMIGLXTD-UHFFFAOYSA-N copper(II) nitrate Chemical compound [Cu+2].[O-][N+]([O-])=O.[O-][N+]([O-])=O XTVVROIMIGLXTD-UHFFFAOYSA-N 0.000 abstract 2
- RLJMLMKIBZAXJO-UHFFFAOYSA-N lead nitrate Chemical compound [O-][N+](=O)O[Pb]O[N+]([O-])=O RLJMLMKIBZAXJO-UHFFFAOYSA-N 0.000 abstract 2
- 229910052701 rubidium Inorganic materials 0.000 abstract 2
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 abstract 1
- 239000010426 asphalt Substances 0.000 abstract 1
- 238000004090 dissolution Methods 0.000 abstract 1
- PNDPGZBMCMUPRI-UHFFFAOYSA-N iodine Chemical compound II PNDPGZBMCMUPRI-UHFFFAOYSA-N 0.000 abstract 1
- 229910052722 tritium Inorganic materials 0.000 abstract 1
- 238000004017 vitrification Methods 0.000 abstract 1
Classifications
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B26/00—Obtaining alkali, alkaline earth metals or magnesium
- C22B26/10—Obtaining alkali metals
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Chemical & Material Sciences (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Geology (AREA)
- Environmental & Geological Engineering (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Manufacturing & Machinery (AREA)
- Plasma & Fusion (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Extraction Or Liquid Replacement (AREA)
Priority Applications (6)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR7639569A FR2376499A1 (fr) | 1976-12-30 | 1976-12-30 | Procede d'extraction de produits de fission contenus dans des elements combustibles nucleaires irradies |
| FR7730371A FR2405541A2 (fr) | 1976-12-30 | 1977-10-10 | Procede d'extraction de produits de fission contenus dans des elements combustibles nucleaires irradies |
| GB5189077A GB1552205A (en) | 1976-12-30 | 1977-12-13 | Extraction of fission products |
| US05/860,452 US4180476A (en) | 1976-12-30 | 1977-12-14 | Process for the extraction of fission products |
| JP16093977A JPS5390598A (en) | 1976-12-30 | 1977-12-28 | Method of extracting nuclear fission product |
| DE19772758408 DE2758408A1 (de) | 1976-12-30 | 1977-12-28 | Verfahren zur abtrennung von spaltprodukten |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR7639569A FR2376499A1 (fr) | 1976-12-30 | 1976-12-30 | Procede d'extraction de produits de fission contenus dans des elements combustibles nucleaires irradies |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| FR2376499A1 true FR2376499A1 (fr) | 1978-07-28 |
| FR2376499B1 FR2376499B1 (enrdf_load_stackoverflow) | 1979-04-27 |
Family
ID=9181739
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| FR7639569A Granted FR2376499A1 (fr) | 1976-12-30 | 1976-12-30 | Procede d'extraction de produits de fission contenus dans des elements combustibles nucleaires irradies |
Country Status (1)
| Country | Link |
|---|---|
| FR (1) | FR2376499A1 (enrdf_load_stackoverflow) |
-
1976
- 1976-12-30 FR FR7639569A patent/FR2376499A1/fr active Granted
Non-Patent Citations (1)
| Title |
|---|
| NEANT * |
Also Published As
| Publication number | Publication date |
|---|---|
| FR2376499B1 (enrdf_load_stackoverflow) | 1979-04-27 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| ST | Notification of lapse |