GB873171A - Production of u - Google Patents

Production of u

Info

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
Application number
GB30680/45A
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Publication of GB873171A publication Critical patent/GB873171A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21GCONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G1/00Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
    • G21G1/02Arrangements 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.
GB30680/45A 1944-11-03 1945-11-15 Production of u Expired GB873171A (en)

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)

* Cited by examiner, † Cited by third party
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

Cited By (2)

* Cited by examiner, † Cited by third party
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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