GB873171A - Production of u - Google Patents
Production of uInfo
- Publication number
- GB873171A GB873171A GB30680/45A GB3068045A GB873171A GB 873171 A GB873171 A GB 873171A GB 30680/45 A GB30680/45 A GB 30680/45A GB 3068045 A GB3068045 A GB 3068045A GB 873171 A GB873171 A GB 873171A
- Authority
- GB
- United Kingdom
- Prior art keywords
- uranium
- thorium
- dissolving
- precipitating
- hydrochloric acid
- 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
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
- G21G1/02—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
873,171. Nuclear reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Nov. 15, 1945 [Nov. 3, 1944], No. 30680/45. Class 39(4). Uranium 233 is produced by subjecting thorium to the action of neutrons the majority of which have an energy of below 1 mev. and by terminating this reaction before the ratio of uranium 233 to thorium is about 1 to 100. Preferably the reaction is terminated when the ratio of uranium 233 plus protoactinium 233 to thorium is between 1 to 1 million and 1 to ten thousand. The thorium is bombarded with 10<SP>15</SP> neutrons per second for a period of at least one month. The neutrons may be obtained from a fast neutron source using . moderator materials containing carbon, deuterium or hydrogen; such as graphite, paraffin, water or heavy water. The reason for terminating the reaction at the specified stage is to prevent excessive wastage of uranium 233 by fission. It is preferred that the thorium should not contain more than sufficient natural uranium to dilute the uranium 233 by more than 20%. The uranium may be extracted by dissolving the thorium compound in nitric or hydrochloric acid, adjusting to pH of about 3 and precipitating both uranium and thorium with an excess of hydrogen peroxide. After removal of the supernatant liquid the precipitate is treated with alkali such as sodium hydroxide and a solution containing the uranium peroxide but not the thorium peroxide results. The uranium may then be separated by acidifying with nitric or hydrochloric acid. The fission products precipitated with the uranium at this stage may be separated by dissolving and precipitating several times. Alternatively the fission products may be removed by crystallizing out uranyl nitrate hexahydrate and dissolving this compound in ether. In an alternative process the thorium is precipitated as a fluoride, iodate, oxylate or phosphate. In the foregoing process the protoactinium is removed with the thorium but it may be separately processed by means of manganese dioxide precipitates dissolved in a mixture of hydrogen peroxide and hydrochloric acid, adding zirconium oxychloride and precipitating the zirconium as zirconium phosphate. Further details of the process are described -in Specification 30681/45.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US873171XA | 1944-11-03 | 1944-11-03 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB873171A true GB873171A (en) | 1961-07-19 |
Family
ID=22204444
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB30680/45A Expired GB873171A (en) | 1944-11-03 | 1945-11-15 | Production of u |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB873171A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4344912A (en) * | 1980-06-16 | 1982-08-17 | The United States Of America As Represented By The United States Department Of Energy | Method of increasing the deterrent to proliferation of nuclear fuels |
CN112048100A (en) * | 2020-09-09 | 2020-12-08 | 巢湖市方太渔具有限责任公司 | Preparation method of fishing net thread quality enhancer |
-
1945
- 1945-11-15 GB GB30680/45A patent/GB873171A/en not_active Expired
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4344912A (en) * | 1980-06-16 | 1982-08-17 | The United States Of America As Represented By The United States Department Of Energy | Method of increasing the deterrent to proliferation of nuclear fuels |
CN112048100A (en) * | 2020-09-09 | 2020-12-08 | 巢湖市方太渔具有限责任公司 | Preparation method of fishing net thread quality enhancer |
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