[go: up one dir, main page]

RU98103625A - METHOD FOR PRODUCING AND ISOLATING SHELLED MOLYBDENE-99 FROM A LIQUID HOMOGENEOUS PHASE CONTAINING URANIUM - Google Patents

METHOD FOR PRODUCING AND ISOLATING SHELLED MOLYBDENE-99 FROM A LIQUID HOMOGENEOUS PHASE CONTAINING URANIUM

Info

Publication number
RU98103625A
RU98103625A RU98103625/06A RU98103625A RU98103625A RU 98103625 A RU98103625 A RU 98103625A RU 98103625/06 A RU98103625/06 A RU 98103625/06A RU 98103625 A RU98103625 A RU 98103625A RU 98103625 A RU98103625 A RU 98103625A
Authority
RU
Russia
Prior art keywords
isolating
producing
phase containing
homogeneous phase
molybdene
Prior art date
Application number
RU98103625/06A
Other languages
Russian (ru)
Other versions
RU2145127C1 (en
Inventor
Г.Ф. Бебих
В.А. Павшук
Н.Н. Пономарев-Степной
П.С. Трухляев
В.Е. Хвостионов
И.К. Швецов
Original Assignee
Российский научный центр "Курчатовский институт"
Filing date
Publication date
Application filed by Российский научный центр "Курчатовский институт" filed Critical Российский научный центр "Курчатовский институт"
Priority to RU98103625A priority Critical patent/RU2145127C1/en
Priority claimed from RU98103625A external-priority patent/RU2145127C1/en
Publication of RU98103625A publication Critical patent/RU98103625A/en
Application granted granted Critical
Publication of RU2145127C1 publication Critical patent/RU2145127C1/en

Links

Claims (2)

1. Способ получения и выделения осколочного молибдена-99 из жидкой гомогенной фазы, содержащей уран, путем облучения в ядерном реакторе, отличающийся тем, что облучают уранилсульфатный топливный раствор, а выделение молибдена ведут на высокомолекулярном сорбенте с селективностью по молибдену-99 выше 90%.1. A method for producing and isolating molybdenum-99 fragment from a liquid homogeneous phase containing uranium by irradiation in a nuclear reactor, characterized in that the uranyl sulfate fuel solution is irradiated, and the molybdenum is isolated on a high molecular weight sorbent with molybdenum-99 selectivity higher than 90%. 2. Способ по п. 1, отличающийся тем, что высокомолекулярный сорбент представляет собой твердый сополимер малеинового ангидрида с привитым к его макромолекулам α-бензоиноксимом. 2. The method according to p. 1, characterized in that the high molecular weight sorbent is a solid copolymer of maleic anhydride grafted to its macromolecules α-benzooxim.
RU98103625A 1998-02-26 1998-02-26 Method for producing and separating fission molybdenum-99 from uranium-containing homogeneous liquid phase RU2145127C1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
RU98103625A RU2145127C1 (en) 1998-02-26 1998-02-26 Method for producing and separating fission molybdenum-99 from uranium-containing homogeneous liquid phase

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
RU98103625A RU2145127C1 (en) 1998-02-26 1998-02-26 Method for producing and separating fission molybdenum-99 from uranium-containing homogeneous liquid phase

Publications (2)

Publication Number Publication Date
RU98103625A true RU98103625A (en) 1999-11-20
RU2145127C1 RU2145127C1 (en) 2000-01-27

Family

ID=20202787

Family Applications (1)

Application Number Title Priority Date Filing Date
RU98103625A RU2145127C1 (en) 1998-02-26 1998-02-26 Method for producing and separating fission molybdenum-99 from uranium-containing homogeneous liquid phase

Country Status (1)

Country Link
RU (1) RU2145127C1 (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2413020C1 (en) * 2009-12-03 2011-02-27 Николай Антонович Ермолов Procedure and device for production of molybdenum-99
RU2489501C1 (en) * 2011-12-01 2013-08-10 Общество с ограниченной ответственностью "Прайм-Инвест" COMPOSITION OF EXTRACTION-CHROMATOGRAPHIC MATERIAL FOR SELECTIVE EXTRACTION OF Mo-99 FROM IRRADIATED URANIUM FUEL
WO2016105235A1 (en) * 2014-12-26 2016-06-30 Акционерное Общество "Ордена Ленина Научно-Исследовательский И Конструкторский Институт Энерготехники Имени Н.А. Доллежаля" Reactor facility for producing an isotope product

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3799883A (en) * 1971-06-30 1974-03-26 Union Carbide Corp Production of high purity fission product molybdenum-99
US5596611A (en) * 1992-12-08 1997-01-21 The Babcock & Wilcox Company Medical isotope production reactor
RU2102807C1 (en) * 1996-07-05 1998-01-20 Товарищество с ограниченной ответственностью Фирма "Изомер-Эффект" Method for producing molybdenum radioisotope

Similar Documents

Publication Publication Date Title
CA2058972A1 (en) Process and installation for treating liquids charged with pollutants
JPS5734251A (en) Address conversion and generating system
RU98103625A (en) METHOD FOR PRODUCING AND ISOLATING SHELLED MOLYBDENE-99 FROM A LIQUID HOMOGENEOUS PHASE CONTAINING URANIUM
RU98117069A (en) METHOD FOR PROCESSING SPENT NUCLEAR FUEL
GB1436465A (en) Methods of operating at least two nuclear reactors
CA2045809A1 (en) Transmutation treatment of radioactive wastes
WO2001003142B1 (en) Accelerator-driven energy generation from thorium
RU95115923A (en) METHOD FOR FORMING A NEUTRON BEAM FOR NEUTRON-CAPTURE THERAPY (NRT)
JPS5321399A (en) Detergent for removing radioactive contamination and its washed water liquid treating method
RU94028125A (en) Method for producing fission nuclides
RU96111306A (en) METHOD OF IRRADIATION OF MINERALS
RU96105356A (en) FUEL ASSEMBLY OF THE NUCLEAR REACTOR
SE8803032D0 (en) SETTING TO REGULATE N-16 RADIATION LEVELS IN THE BASKET WATER REACTORS ANG phase
JPS51130800A (en) Treatment method by exchange,adsorption,separation,enrichment of cesiu m-137 from radio-active waste liquid
Tatsumi et al. Some studies on the postpolymerization of methyl methacrylate irradiated with UV
Grechukhin et al. Conversion of low-energy (hω/2π<= 3 keV) nuclear transitions on outer electron shells of a free atom
JPS52137600A (en) Tritium in waste water removing method in atomic energy plant
Dubasov et al. Nuclear fuel containing particles of the Chernobyl NPP 30-km area as a potential source of radionuclide contamination of natural water; Toplivosoderzhashchie chastitsy 30-km zony Chernobylskoj AEhS kak potentsia lnyj istochnik zagryazneniya prirodnykh vod radionuklidami
RU95120517A (en) METHOD FOR REFINING OIL AND OIL PRODUCTS
Alekseev et al. Slow neutron pulse source
Carley-Macauly Options for the treatment of low-and intermediate-level active liquid wastes
Popov et al. Analysis of reactor vessel integrity on the base of finite element method.; Analiz tselostnosti korpusa reaktora na osnove MKEh.
SU611510A1 (en) Device for irradiating materials in nuclear reactor
JPS5211291A (en) Preparation of polyene-maleic anhydride graft copolymer
JPS5219895A (en) Broken fuel inspection apparatus