GB1111959A - Method for the electronic regulation of a plutonium extraction battery - Google Patents
Method for the electronic regulation of a plutonium extraction batteryInfo
- Publication number
- GB1111959A GB1111959A GB2899266A GB2899266A GB1111959A GB 1111959 A GB1111959 A GB 1111959A GB 2899266 A GB2899266 A GB 2899266A GB 2899266 A GB2899266 A GB 2899266A GB 1111959 A GB1111959 A GB 1111959A
- Authority
- GB
- United Kingdom
- Prior art keywords
- plutonium
- june
- flow rate
- aqueous solution
- detectors
- 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
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
-
- 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
- G21F9/12—Processing by absorption; by adsorption; by ion-exchange
- G21F9/125—Processing by absorption; by adsorption; by ion-exchange by solvent extraction
-
- 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)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- Extraction Or Liquid Replacement (AREA)
- Other Investigation Or Analysis Of Materials By Electrical Means (AREA)
Abstract
1,111,959. Processing spent nuclear fuel. COMMISSARIAT A L'ENERGIE ATOMIQUE. 28 June, 1966 [29 June, 1965], No. 28992/66. Heading G6R. [Also in Division G3] In the separation of uranium and plutonium from fission products by countercurrent extraction of an aqueous solution with a solvent, for example tributyl phosphate, the process is regulated electronically by measuring the plutonium retention in intermediate extraction stages by means of a neutron detector in each stage, integrating the impulses received from the detectors to provide a voltage which drives a motor associated with the feeding means for one of the liquid phases, so as to vary the ratio of the solvent flow rate to the aqueous solution flow rate. The neutron detectors may comprise cylindrical copper cathodes and coaxial anodes and may be filled with BF 3 enriched with B10. An alarm is provided to warn of excessive plutonium leakage.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR22824A FR1455188A (en) | 1965-06-29 | 1965-06-29 | Method of electronic regulation of a plutonium extraction battery, and corresponding apparatus |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1111959A true GB1111959A (en) | 1968-05-01 |
Family
ID=8583389
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB2899266A Expired GB1111959A (en) | 1965-06-29 | 1966-06-28 | Method for the electronic regulation of a plutonium extraction battery |
Country Status (10)
Country | Link |
---|---|
US (1) | US3454366A (en) |
BE (1) | BE682953A (en) |
CH (1) | CH458559A (en) |
DE (1) | DE1592239B2 (en) |
FR (1) | FR1455188A (en) |
GB (1) | GB1111959A (en) |
IL (1) | IL26009A (en) |
LU (1) | LU51417A1 (en) |
NL (1) | NL6608952A (en) |
SE (1) | SE312871B (en) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN113968647B (en) * | 2021-12-27 | 2022-03-29 | 广东新泰隆环保集团有限公司 | Multiple combination formula sewage treatment device |
CN118079450B (en) * | 2024-04-26 | 2024-07-19 | 四川省畜牧科学研究院 | Auxiliary extraction device and extraction method for sinapine in rapeseed meal |
Family Cites Families (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2882124A (en) * | 1945-10-12 | 1959-04-14 | Glenn T Seaborg | Solvent extraction process for plutonium |
US2893822A (en) * | 1949-08-16 | 1959-07-07 | Herbert H Hyman | Separation of uranium from other metals |
US2893824A (en) * | 1950-04-19 | 1959-07-07 | Herbert H Hyman | Uranium recovery process |
US3050624A (en) * | 1958-03-14 | 1962-08-21 | Siemens Ag | Neutron-flux gage for nuclear reactors |
US3141092A (en) * | 1961-06-09 | 1964-07-14 | Leo H Weinberg | Selector for fast and intermediate energy neutrons positioned within moderator and absorber shields |
US3225200A (en) * | 1961-08-11 | 1965-12-21 | Commissariat Energie Atomique | Determination of the number of neutrons emitted simultaneously by a source |
FR1305502A (en) * | 1961-08-11 | 1962-10-05 | Commissariat Energie Atomique | Method and devices for determining among the neutrons emitted by a source the number of those appearing simultaneously |
GB1031194A (en) * | 1962-04-02 | 1966-06-02 | Nihon Genshiryoku Kenkyu Sho | Improvements in the fractionation of aqueous solutions |
US3332744A (en) * | 1963-09-03 | 1967-07-25 | Texas Gulf Sulphur Co | Radiometric method for plant stream control in potash and phosphate recovery processes |
US3381131A (en) * | 1965-05-04 | 1968-04-30 | Reuter Stokes Electronic Compo | Neutron detector for operation in high gamma fluxes |
-
1965
- 1965-06-29 FR FR22824A patent/FR1455188A/en not_active Expired
-
1966
- 1966-06-21 US US3454366D patent/US3454366A/en not_active Expired - Lifetime
- 1966-06-21 IL IL26009A patent/IL26009A/en unknown
- 1966-06-22 BE BE682953D patent/BE682953A/xx unknown
- 1966-06-27 LU LU51417A patent/LU51417A1/xx unknown
- 1966-06-28 NL NL6608952A patent/NL6608952A/xx unknown
- 1966-06-28 GB GB2899266A patent/GB1111959A/en not_active Expired
- 1966-06-28 CH CH932566A patent/CH458559A/en unknown
- 1966-06-29 SE SE887666A patent/SE312871B/xx unknown
- 1966-06-29 DE DE19661592239 patent/DE1592239B2/en not_active Withdrawn
Also Published As
Publication number | Publication date |
---|---|
SE312871B (en) | 1969-07-28 |
DE1592239A1 (en) | 1971-12-09 |
NL6608952A (en) | 1966-12-30 |
IL26009A (en) | 1970-05-21 |
FR1455188A (en) | 1966-04-01 |
CH458559A (en) | 1968-06-30 |
US3454366A (en) | 1969-07-08 |
LU51417A1 (en) | 1966-08-29 |
DE1592239B2 (en) | 1971-12-09 |
BE682953A (en) | 1966-12-01 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
ES368454A1 (en) | Irradiated fuel recovery system | |
GB923083A (en) | Improvements in/or relating to the monitoring of fission products in a gaseous stream, particularly for detecting burst slugs in nuclear reactors | |
Levine et al. | Half-life for double beta-decay | |
GB1111959A (en) | Method for the electronic regulation of a plutonium extraction battery | |
GB1436465A (en) | Methods of operating at least two nuclear reactors | |
GB1306408A (en) | Reprocessing method for fuel and or breeder elements of nuclear reactors | |
GB1452115A (en) | Method of selective stripping of plutonium for organic solvents loaded with plutonium | |
GB1378409A (en) | Electrolytic process for the separation of plutonium | |
GB1247248A (en) | A method of recovering plutonium and uranium from fission products by liquid-liquid extraction | |
ES306340A1 (en) | Method of separation of uranium from plutonium | |
GB1330535A (en) | Processing of irradiated nuclear reactor fuel | |
GB1260096A (en) | Organic phase reduction of uranium | |
GB1362410A (en) | Process for separating uranium and thorium from spent nuclear fuels | |
GB1455095A (en) | Process for the recovery of americium curium and other actinide | |
GB862352A (en) | Process for the reduction of plutonium | |
GB1490900A (en) | Apparatus for performing liquid-liquid exchange by centrifugation | |
GB1153237A (en) | A Method of Selective Reduction of Plutonium Hexafluoride and Apparatus for carrying out said Method | |
GB1304313A (en) | ||
GB1205736A (en) | Purification of transplutonium elements | |
GB1352329A (en) | Method and apparatus for handling liquids containing fissile material | |
GB1205169A (en) | Improvements in or relating to the processing or irradiated nuclear fuel | |
FR2085603A1 (en) | Processing of nuclear fuel rods | |
GB1349982A (en) | Preparation of solutions of mixed uranium and plutonium nitrates | |
GB1131578A (en) | Improvements in and relating to a liquid-liquid extraction process | |
GB1219146A (en) | Recovery of plutonium and uranium from reactor fuel elements |