GB1187369A - Process and Apparatus for the Semicontinuous Dissolution of Spent Nuclear Reactor Fuel - Google Patents
Process and Apparatus for the Semicontinuous Dissolution of Spent Nuclear Reactor FuelInfo
- Publication number
- GB1187369A GB1187369A GB1567569A GB1567569A GB1187369A GB 1187369 A GB1187369 A GB 1187369A GB 1567569 A GB1567569 A GB 1567569A GB 1567569 A GB1567569 A GB 1567569A GB 1187369 A GB1187369 A GB 1187369A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel
- leg
- dissolving unit
- housing
- solvent
- 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
- 239000003758 nuclear fuel Substances 0.000 title abstract 2
- 238000004090 dissolution Methods 0.000 title 1
- 238000000034 method Methods 0.000 title 1
- 239000000446 fuel Substances 0.000 abstract 4
- 239000002904 solvent Substances 0.000 abstract 3
- 239000007789 gas Substances 0.000 abstract 2
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 abstract 1
- 238000001816 cooling Methods 0.000 abstract 1
- 238000010438 heat treatment Methods 0.000 abstract 1
- 239000007788 liquid Substances 0.000 abstract 1
- 229910017604 nitric acid Inorganic materials 0.000 abstract 1
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract 1
- 239000000126 substance Substances 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
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
-
- 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
-
- 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)
- Chemical & Material Sciences (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Organic Chemistry (AREA)
- General Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Geology (AREA)
- Inorganic Chemistry (AREA)
- Processing Of Solid Wastes (AREA)
- Solid Fuels And Fuel-Associated Substances (AREA)
Abstract
1,187,369. Extracting from nuclear fuels. ALLIED CHEMICAL CORP. 25 March, 1969 [2 April, 1968; 4 Sept., 1968], No. 15675/69. Heading B1Q. [Also in Division G6] A dissolving unit for spent nuclear fuel comprises a main housing 13 open at 20 and having a solvent inlet 14, a recycle housing 23, and a solution outlet 25. Chopped or sheared fuel elements are introduced at 2 into pivotted bucket member 6 which may be tilted to discharge through leg 3 into dissolving unit 5 containing perforated basket 12 immersed in solvent, for example nitric acid, or through leg 4 into a twin dissolving unit, not shown. The liquid is circulated by means of a pressure differential caused by the action of heating jacket 17 or cooling jacket 27 or by introducing gas into the housing 13. Effluent gases are removed at 24. When the solution reaches a predetermined maximum strength, fresh solvent is added at 14 and solution is removed at 25 until a predetermined minimum strength is reached when the addition and removal are stopped. When all the fuel has dissolved, the residue may be washed and removed, while the fuel to be dissolved is diverted to the other dissolver via leg 4. A slightly different feeding means for the fuel element pieces is described with reference to Figure 2, not shown.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US71817568A | 1968-04-02 | 1968-04-02 | |
| US77793368A | 1968-09-04 | 1968-09-04 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1187369A true GB1187369A (en) | 1970-04-08 |
Family
ID=27109853
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB1567569A Expired GB1187369A (en) | 1968-04-02 | 1969-03-25 | Process and Apparatus for the Semicontinuous Dissolution of Spent Nuclear Reactor Fuel |
Country Status (4)
| Country | Link |
|---|---|
| BE (1) | BE730601A (en) |
| DE (1) | DE1916753A1 (en) |
| FR (1) | FR2005408A1 (en) |
| GB (1) | GB1187369A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0076116A2 (en) * | 1981-09-29 | 1983-04-06 | United Kingdom Atomic Energy Authority | Agitator apparatus |
| DE3336390A1 (en) * | 1983-10-06 | 1985-04-25 | Nukem Gmbh, 6450 Hanau | Process for dissolving burnt-up nuclear fuels |
| CN103550950A (en) * | 2013-11-04 | 2014-02-05 | 广东果美乐食品有限公司 | Circulating steam heating type longan pulp nutrient solution extracting tank |
| CN111584111A (en) * | 2020-05-15 | 2020-08-25 | 中国原子能科学研究院 | Dissolver for spent fuel element and treatment method of dissolving liquid |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4294805A (en) * | 1978-08-09 | 1981-10-13 | United Kingdom Atomic Energy Authority | Method of leaching the contents of a can |
| FR3113408B1 (en) | 2020-08-11 | 2022-08-12 | Capsum | Fluid product dispensing mechanism, intended for a product dispensing machine and associated machine |
| FR3115995B1 (en) | 2020-11-09 | 2022-10-28 | Capsum | Apparatus for decontaminating a hollow object defining an internal cavity, dispensing machine and associated method |
| FR3119317B1 (en) | 2021-02-04 | 2024-05-03 | Capsum | Composition in the form of a stable macroscopic emulsion comprising a percentage of ingredients of natural origin greater than or equal to 95% according to standard ISO 16128 |
-
1969
- 1969-03-25 GB GB1567569A patent/GB1187369A/en not_active Expired
- 1969-03-27 BE BE730601D patent/BE730601A/xx unknown
- 1969-04-01 DE DE19691916753 patent/DE1916753A1/en active Pending
- 1969-04-02 FR FR6910094A patent/FR2005408A1/en active Granted
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0076116A2 (en) * | 1981-09-29 | 1983-04-06 | United Kingdom Atomic Energy Authority | Agitator apparatus |
| EP0076116A3 (en) * | 1981-09-29 | 1984-08-01 | United Kingdom Atomic Energy Authority | Agitator apparatus |
| DE3336390A1 (en) * | 1983-10-06 | 1985-04-25 | Nukem Gmbh, 6450 Hanau | Process for dissolving burnt-up nuclear fuels |
| CN103550950A (en) * | 2013-11-04 | 2014-02-05 | 广东果美乐食品有限公司 | Circulating steam heating type longan pulp nutrient solution extracting tank |
| CN103550950B (en) * | 2013-11-04 | 2016-03-30 | 广东果美乐食品有限公司 | Vapor recycle heated type dried longan pulp nutrient solution extractor |
| CN111584111A (en) * | 2020-05-15 | 2020-08-25 | 中国原子能科学研究院 | Dissolver for spent fuel element and treatment method of dissolving liquid |
Also Published As
| Publication number | Publication date |
|---|---|
| DE1916753A1 (en) | 1969-11-06 |
| BE730601A (en) | 1969-09-01 |
| FR2005408B1 (en) | 1974-05-03 |
| FR2005408A1 (en) | 1969-12-12 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PS | Patent sealed | ||
| PLNP | Patent lapsed through nonpayment of renewal fees |