GB832506A - Improvements in or relating to a process for the treatment of an aqueous homogeneousnuclear reactor fuel - Google Patents

Improvements in or relating to a process for the treatment of an aqueous homogeneousnuclear reactor fuel

Info

Publication number
GB832506A
GB832506A GB6387/56A GB638756A GB832506A GB 832506 A GB832506 A GB 832506A GB 6387/56 A GB6387/56 A GB 6387/56A GB 638756 A GB638756 A GB 638756A GB 832506 A GB832506 A GB 832506A
Authority
GB
United Kingdom
Prior art keywords
sulphate
iodine
reactor fuel
solution
homogeneousnuclear
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
GB6387/56A
Inventor
Eugen Glueckauf
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
Priority to GB6387/56A priority Critical patent/GB832506A/en
Publication of GB832506A publication Critical patent/GB832506A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/42Reprocessing of irradiated fuel
    • G21C19/50Reprocessing of irradiated fuel of irradiated fluid fuel, e.g. regeneration of fuels while the reactor is in operation
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00Compounds of uranium
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Inorganic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Treating Waste Gases (AREA)

Abstract

Fission products are removed from a nuclear reactor fuel comprising a homogeneous aqueous solution of uranyl sulphate by adding to the solution a chemical substance which increases the rate of formation of a separate phase containing the fission products. Addition of a sulphate of cerium, aluminium, chromium, or iron assists the precipitation of rare earth sulphates; the rate of precipitation of fission product strontium and barium sulphates is increased by adding barium sulphate. To remove halogens, silver sulphate, with or without iodine, is added to precipitate silver halides; alternatively iodine may be separated as a gaseous phase by feeding a gaseous stream of natural iodine through the solution.
GB6387/56A 1956-02-29 1956-02-29 Improvements in or relating to a process for the treatment of an aqueous homogeneousnuclear reactor fuel Expired GB832506A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB6387/56A GB832506A (en) 1956-02-29 1956-02-29 Improvements in or relating to a process for the treatment of an aqueous homogeneousnuclear reactor fuel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB6387/56A GB832506A (en) 1956-02-29 1956-02-29 Improvements in or relating to a process for the treatment of an aqueous homogeneousnuclear reactor fuel

Publications (1)

Publication Number Publication Date
GB832506A true GB832506A (en) 1960-04-13

Family

ID=9813587

Family Applications (1)

Application Number Title Priority Date Filing Date
GB6387/56A Expired GB832506A (en) 1956-02-29 1956-02-29 Improvements in or relating to a process for the treatment of an aqueous homogeneousnuclear reactor fuel

Country Status (1)

Country Link
GB (1) GB832506A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2422711A1 (en) * 1974-05-10 1975-11-20 Kernkraftwerk Bayernwerk Gmbh Removal of radioactive iodine from aq. solns. - by two-step pptn. jointly with other radioactive isotopes

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2422711A1 (en) * 1974-05-10 1975-11-20 Kernkraftwerk Bayernwerk Gmbh Removal of radioactive iodine from aq. solns. - by two-step pptn. jointly with other radioactive isotopes

Similar Documents

Publication Publication Date Title
GB1388497A (en) Process for the separation of components from gas mixtures
GB1115920A (en) Treatment of nuclear fuels
GB1361366A (en) Removal of organic and inorganic iodine from a gaseous atmosphere
GB895366A (en) Process for the production of glass
GB832506A (en) Improvements in or relating to a process for the treatment of an aqueous homogeneousnuclear reactor fuel
GB1075233A (en) Improvements in or relating to the production of uranyl fluoride
GB1193596A (en) Ion Exchange Process for Recovering Americium and Curium.
GB933807A (en) Aluminium cladding dissolution
GB1400367A (en) Method for removing alkyl iodides from air by mercuric nitrate solution
FR1335072A (en) Process for the separation of uranium, plutonium and fission products from uranium bombarded by neutrons
GB1047232A (en)
GB1068104A (en) Dissolution of nuclear fuel
GB1026213A (en) Improvements in or relating to iodineí¬131
GB981532A (en) Dissolution of uranium-molybdenum and/or uraniummolybdenum-plutonium reactor fuel elements
GB1206038A (en) Process for the separation of elements of the lanthanide group or elements of the transplutonium group which are present in an aqueous group
GB1083957A (en) Improvements relating to methods of preparing tungstic acid
GB946598A (en) Radioactive iodine process
GB1171268A (en) Recovery of Mercury from Solutions
ES388664A1 (en) Process for the recovery of ammonium sulphate from it aqueous solutions contaminated by organic substances
GB877333A (en) Manufacture of radioactive iodine
GB896758A (en) Improvements in or relating to the separation of technetium from fission product solutions
GB1221604A (en) A method of processing nuclear fuels
Deptuła et al. Separation of trace impurities of 131 I from 99 Mo obtained by extraction from fission products of uranium
GB879041A (en) Improvements in or relating to the processing of nuclear reactor fuel elements
GB1158535A (en) Method of making Uranium Dioxide more Reactive