GB1240517A - Process and apparatus for the continuous dissolving treatment of sheathed nuclear fuels with a liquid - Google Patents
Process and apparatus for the continuous dissolving treatment of sheathed nuclear fuels with a liquidInfo
- Publication number
- GB1240517A GB1240517A GB50589/68A GB5058968A GB1240517A GB 1240517 A GB1240517 A GB 1240517A GB 50589/68 A GB50589/68 A GB 50589/68A GB 5058968 A GB5058968 A GB 5058968A GB 1240517 A GB1240517 A GB 1240517A
- Authority
- GB
- United Kingdom
- Prior art keywords
- liquid
- dissolving
- baskets
- rinsing
- figures
- 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
- 239000007788 liquid Substances 0.000 title abstract 5
- 239000003758 nuclear fuel Substances 0.000 title abstract 3
- 238000000034 method Methods 0.000 title abstract 2
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 abstract 3
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 abstract 2
- 229910017604 nitric acid Inorganic materials 0.000 abstract 2
- 229910000838 Al alloy Inorganic materials 0.000 abstract 1
- 229910001093 Zr alloy Inorganic materials 0.000 abstract 1
- 239000002253 acid Substances 0.000 abstract 1
- 239000000446 fuel Substances 0.000 abstract 1
- 239000000843 powder Substances 0.000 abstract 1
- 230000005855 radiation Effects 0.000 abstract 1
- 238000010008 shearing Methods 0.000 abstract 1
- 235000011121 sodium hydroxide Nutrition 0.000 abstract 1
- 239000011343 solid material Substances 0.000 abstract 1
- 239000010935 stainless steel Substances 0.000 abstract 1
- 229910001256 stainless steel alloy Inorganic materials 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
- G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
- G21C19/38—Chemical means only
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Manufacture And Refinement Of Metals (AREA)
- Cleaning By Liquid Or Steam (AREA)
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR167264 | 1968-09-24 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1240517A true GB1240517A (en) | 1971-07-28 |
Family
ID=8654857
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB50589/68A Expired GB1240517A (en) | 1968-09-24 | 1968-10-24 | Process and apparatus for the continuous dissolving treatment of sheathed nuclear fuels with a liquid |
Country Status (10)
| Country | Link |
|---|---|
| JP (1) | JPS5214400B1 (enExample) |
| BE (1) | BE721798A (enExample) |
| BR (1) | BR6803153D0 (enExample) |
| DE (1) | DE1815867C3 (enExample) |
| ES (1) | ES359808A1 (enExample) |
| FR (1) | FR1602368A (enExample) |
| GB (1) | GB1240517A (enExample) |
| LU (1) | LU57035A1 (enExample) |
| NL (1) | NL6815370A (enExample) |
| SE (1) | SE349685B (enExample) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0060648A1 (en) * | 1981-03-13 | 1982-09-22 | United Kingdom Atomic Energy Authority | A method of dissolving nuclear material from a nuclear fuel cartridge, and apparatus therefor |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2944197A1 (de) * | 1979-11-02 | 1981-05-14 | Gesellschaft zur Wiederaufbereitung von Kernbrennstoffen mbH, 7514 Eggenstein-Leopoldshafen | Fernbedienbare schere zum abschnittweisen zerschneiden von bestrahlten kernbrennstoffstaeben oder -stabbuendeln |
| DE3017674C2 (de) * | 1980-05-08 | 1982-05-27 | Kraftwerk Union AG, 4330 Mülheim | Verfahren und Einrichtung zur Aufbereitung von Kernbrennstoffen |
-
1968
- 1968-09-24 FR FR167264A patent/FR1602368A/fr not_active Expired
- 1968-10-03 BE BE721798D patent/BE721798A/xx unknown
- 1968-10-04 LU LU57035D patent/LU57035A1/xx unknown
- 1968-10-07 SE SE13516/68A patent/SE349685B/xx unknown
- 1968-10-11 JP JP43073567A patent/JPS5214400B1/ja active Pending
- 1968-10-15 BR BR203153/68A patent/BR6803153D0/pt unknown
- 1968-10-24 GB GB50589/68A patent/GB1240517A/en not_active Expired
- 1968-10-28 NL NL6815370A patent/NL6815370A/xx unknown
- 1968-10-31 ES ES359808A patent/ES359808A1/es not_active Expired
- 1968-12-19 DE DE1815867A patent/DE1815867C3/de not_active Expired
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0060648A1 (en) * | 1981-03-13 | 1982-09-22 | United Kingdom Atomic Energy Authority | A method of dissolving nuclear material from a nuclear fuel cartridge, and apparatus therefor |
| US4769222A (en) * | 1981-03-13 | 1988-09-06 | United Kingdom Atomic Energy Authority | Method of dissolving nuclear material from a nuclear fuel cartridge |
Also Published As
| Publication number | Publication date |
|---|---|
| BR6803153D0 (pt) | 1973-01-09 |
| LU57035A1 (enExample) | 1969-06-25 |
| ES359808A1 (es) | 1972-01-01 |
| DE1815867A1 (de) | 1970-08-13 |
| DE1815867C3 (de) | 1975-04-10 |
| BE721798A (enExample) | 1969-04-03 |
| DE1815867B2 (de) | 1974-08-22 |
| NL6815370A (enExample) | 1970-03-26 |
| FR1602368A (enExample) | 1970-11-16 |
| SE349685B (enExample) | 1972-10-02 |
| JPS5214400B1 (enExample) | 1977-04-21 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US3393981A (en) | Method of decomposing a nuclear fuel in a fused salt system by using nitric oxide | |
| US3507801A (en) | Entrapment of radioactive waste water using sodium borate | |
| GB1240517A (en) | Process and apparatus for the continuous dissolving treatment of sheathed nuclear fuels with a liquid | |
| GB2157276A (en) | Process for the batch fine purification of uranium or plutonium recovered in a reprocessing process for irradiated nuclear fuel and/or fertile materials | |
| US3120493A (en) | Suppression of ruthenium volatilization in evaporation and calcination of radioactive waste solutions | |
| Aihara et al. | Characterization of the insoluble sludge from the dissolution of irradiated fast breeder reactor fuel | |
| US4297324A (en) | Apparatus for the continuous processing of compounds in a liquid | |
| EP0364209B1 (en) | Method of dissolving spent nuclear fuel | |
| US4312836A (en) | Apparatus for the continuous treatment of the compounds in a corrosive liquid | |
| GB1187369A (en) | Process and Apparatus for the Semicontinuous Dissolution of Spent Nuclear Reactor Fuel | |
| US3222125A (en) | Dissolution of nuclear aluminum-base fuel | |
| US3607107A (en) | Plural spent-reactor-fuel dissolvers having selective feed means | |
| JPH10132999A (ja) | 付着ウラン洗浄除去装置及び洗浄除去方法 | |
| US2852419A (en) | Process of decontaminating material contaminated with radioactivity | |
| US3716616A (en) | Process for decontamination of neutron-irradiated beryllium | |
| GB1171257A (en) | Process and Apparatus for Processing Irradiated Ceramic Fuel Elements | |
| Groenier | Equipment for the dissolution of core material from sheared power reactor fuels | |
| US4950086A (en) | Structure having radioactive plant components | |
| US2934424A (en) | Decontamination of plutoniumaluminum alloy material | |
| Johnson et al. | Light water reactor fuel reprocessing: dissolution studies of voloxidized fuel | |
| DE2110419B2 (de) | Verfahren zur Entmantelung eines Bundeis von Brennelementen | |
| GB811790A (en) | Improvements in or relating to vessels for processing nuclear fuel | |
| GB1292778A (en) | Furnace and method for the pyrochemical processing of nuclear reactor fuel elements | |
| SU132408A1 (ru) | Способ сн ти олова с отходов белой жести | |
| Bokelund et al. | Removal of actinide elements from intermediate level waste solutions by precipitation with oxalic acid |