FR2405541A2 - 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
- FR2405541A2 FR2405541A2 FR7730371A FR7730371A FR2405541A2 FR 2405541 A2 FR2405541 A2 FR 2405541A2 FR 7730371 A FR7730371 A FR 7730371A FR 7730371 A FR7730371 A FR 7730371A FR 2405541 A2 FR2405541 A2 FR 2405541A2
- Authority
- FR
- France
- Prior art keywords
- fission products
- nuclear fuel
- irradied
- fuel elements
- products contained
- 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
- 230000004992 fission Effects 0.000 title abstract 6
- 238000000034 method Methods 0.000 title abstract 3
- 239000003758 nuclear fuel Substances 0.000 title abstract 2
- 239000007864 aqueous solution Substances 0.000 abstract 3
- 239000012141 concentrate Substances 0.000 abstract 2
- 229910052792 caesium Inorganic materials 0.000 abstract 1
- TVFDJXOCXUVLDH-UHFFFAOYSA-N caesium atom Chemical compound [Cs] TVFDJXOCXUVLDH-UHFFFAOYSA-N 0.000 abstract 1
- 238000004090 dissolution Methods 0.000 abstract 1
- 238000004821 distillation Methods 0.000 abstract 1
- 239000000446 fuel Substances 0.000 abstract 1
- PNDPGZBMCMUPRI-UHFFFAOYSA-N iodine Chemical compound II PNDPGZBMCMUPRI-UHFFFAOYSA-N 0.000 abstract 1
- 230000007774 longterm Effects 0.000 abstract 1
- 238000011084 recovery Methods 0.000 abstract 1
- 229910052701 rubidium Inorganic materials 0.000 abstract 1
- IGLNJRXAVVLDKE-UHFFFAOYSA-N rubidium atom Chemical compound [Rb] IGLNJRXAVVLDKE-UHFFFAOYSA-N 0.000 abstract 1
- 239000000243 solution Substances 0.000 abstract 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 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
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/08—Processing by evaporation; by distillation
-
- 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)
- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Mechanical Engineering (AREA)
- Manufacturing & Machinery (AREA)
- Materials Engineering (AREA)
- Life Sciences & Earth Sciences (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Geology (AREA)
- Plasma & Fusion (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Environmental & Geological Engineering (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
Priority Applications (5)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| 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 (2)
| 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 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| FR2405541A2 true FR2405541A2 (fr) | 1979-05-04 |
| FR2405541B2 FR2405541B2 (en:Method) | 1981-06-26 |
Family
ID=26219774
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| FR7730371A Granted FR2405541A2 (fr) | 1976-12-30 | 1977-10-10 | Procede d'extraction de produits de fission contenus dans des elements combustibles nucleaires irradies |
Country Status (5)
| Country | Link |
|---|---|
| US (1) | US4180476A (en:Method) |
| JP (1) | JPS5390598A (en:Method) |
| DE (1) | DE2758408A1 (en:Method) |
| FR (1) | FR2405541A2 (en:Method) |
| GB (1) | GB1552205A (en:Method) |
Families Citing this family (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2277415A1 (fr) * | 1974-07-03 | 1976-01-30 | Commissariat Energie Atomique | Procede d'extraction, de piegeage et de stockage de l'iode radioactif contenu dans les combustibles nucleaires irradies |
| US4582637A (en) * | 1980-03-28 | 1986-04-15 | British Nuclear Fuels Ltd. | Reprocessing of irradiated nuclear fuel |
| DE3103900C2 (de) * | 1981-02-05 | 1984-02-02 | Kernforschungsanlage Jülich GmbH, 5170 Jülich | Anlage zum Aufbereiten graphitischer Brennelemente von Hochtemperatur-Kernreaktoren |
| US4673547A (en) * | 1982-05-24 | 1987-06-16 | Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung | Process for separation of hydrogen and/or deuterium and tritium from an inert gas flow and apparatus for effectuation of process in the cooling gas circuit of a gas-cooled nuclear reactor |
| US4595529A (en) * | 1984-03-13 | 1986-06-17 | The United States Of America As Represented By The Department Of Energy | Solvent wash solution |
| FR2681139B1 (fr) * | 1991-09-10 | 1993-11-05 | Matieres Nucleaires Cie Gle | Installation pour effectuer plusieurs reactions chimiques successives dans un meme recipient. |
| CA2713959C (en) * | 2008-02-05 | 2012-01-31 | The Curators Of The University Of Missouri | Radioisotope production and treatment of solution of target material |
| WO2014071966A1 (en) | 2012-11-12 | 2014-05-15 | Christian-Albrechts-Universität Zu Kiel | Layered titanates of unsaturated amines |
| KR101558920B1 (ko) * | 2013-09-13 | 2015-10-08 | 한국원자력연구원 | 요오드 핵종을 함유하는 방사성 폐수의 생물학적 정화 장치 |
| KR101490355B1 (ko) * | 2014-01-09 | 2015-02-05 | 한국원자력연구원 | 방사성 폐수 내 고농도 요오드의 무기광물화 제거방법 및 제거장치 |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3282655A (en) * | 1966-11-01 | Production of | ||
| GB987014A (en) * | 1962-07-04 | 1965-03-24 | Yarrow & Company Ltd | Improvements in and relating to nuclear reactor installations |
| US3365578A (en) * | 1962-08-10 | 1968-01-23 | Atomic Energy Authority Uk | Glass composition comprising radioactive waste oxide material contained within a steel vessel |
| US3298961A (en) * | 1965-08-26 | 1967-01-17 | George D Davis | Concentration and containment of radioactivity from radioactive waste solutions in asphalt |
| UST939005I4 (en) | 1974-03-20 | 1975-10-07 | Forced circulation |
-
1977
- 1977-10-10 FR FR7730371A patent/FR2405541A2/fr active Granted
- 1977-12-13 GB GB5189077A patent/GB1552205A/en not_active Expired
- 1977-12-14 US US05/860,452 patent/US4180476A/en not_active Expired - Lifetime
- 1977-12-28 DE DE19772758408 patent/DE2758408A1/de not_active Withdrawn
- 1977-12-28 JP JP16093977A patent/JPS5390598A/ja active Pending
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5390598A (en) | 1978-08-09 |
| DE2758408A1 (de) | 1978-07-06 |
| US4180476A (en) | 1979-12-25 |
| FR2405541B2 (en:Method) | 1981-06-26 |
| GB1552205A (en) | 1979-09-12 |
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