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AbstractAbstract
No abstract available
Original Title
Zasedani vedecko-technicke rady RVHP pro zpracovani a zneskodnovani radioaktivnich produktu
Primary Subject
Source
Letter-to-the-editor.
Record Type
Journal Article
Journal
Nukleon; ISSN 0302-8542; ; (no.2); p. 23-24
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AbstractAbstract
[en] A report is presented of the fifth CMEA symposium whose task it was to evaluate the studies implemented in the field in the member states within 1976 and 1980 and to consider the trends for the period 1981-85. (M.D.)
Original Title
Pate symposium RVHP - ''Vyzkumy v oblasti zpracovani vyhoreleho jaderneho paliva a zneskodnovani radioaktivnich odpadu''
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Secondary Subject
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Journal Article
Journal
Nukleon; (no.1); p. 27-28
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AbstractAbstract
No abstract available
Original Title
12. zasedani Vedeckotechnicke rady RVHP pro zpracovani a zneskodnovani radioaktivnich produktu
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Secondary Subject
Source
Letter-to-the-editor.
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Journal Article
Journal
Country of publication
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AbstractAbstract
[en] Economic aspects of U and Pu recycle are discussed with a reference to the WWER-type reactors-based nuclear power in Czechoslovakia. Major results of forecasting the nuclear electricity generating capacities and related spent fuel stockpiles into the year of 2000 are presented. The economic analysis of the spent fuel reprocessing shows that recovered U overlaps the reprocessing costs for reprocessing plants with productivity more than 2 tonnes/day. Pu recycling will increase the effect. The economics of fast breeder reactor spent fuel reprocessing is also considered in a nutshell. Unaccounted reprocessing costs connected with radioactive waste disposal can influence, as stated the overall conclusions
Original Title
Otrabotavshee toplivo chekhoslovatskoj atomnoj ehnergetiki
Primary Subject
Source
Sovet Ehkonomicheskoj Vzaimopomoshchi, Moscow (USSR). Postoyanniya Komissiya po Ispol'zovaniyu Atomnoj Ehnergii v Mirnykh Tselyakh; p. 240-246; 1975; p. 240-246; 3. CMEA symposium on investigations in the field of spent fuel reprocessing; Marianske Lazne, Czechoslovakia; 24 - 26 Apr 1974; 9 refs.; 4 tables.
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, DEVELOPING COUNTRIES, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EUROPE, EVEN-ODD NUCLEI, FUELS, HEAVY NUCLEI, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MINUTES LIVING RADIOISOTOPES, NUCLEAR FACILITIES, NUCLEAR FUELS, NUCLEI, PLUTONIUM ISOTOPES, POWER REACTORS, PWR TYPE REACTORS, RADIOISOTOPES, REACTOR MATERIALS, REACTORS, SEPARATION PROCESSES, THERMAL REACTORS, URANIUM ISOTOPES, WATER COOLED REACTORS, WATER MODERATED REACTORS, YEARS LIVING RADIOISOTOPES
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Zakazkove obohacovani uranu
Primary Subject
Secondary Subject
Record Type
Journal Article
Journal
Jaderna Energie; v. 20(11); p. 387-390
Country of publication
ACTINIDE NUCLEI, ACTINIDES, ALPHA DECAY RADIOISOTOPES, ELEMENTS, EVEN-ODD NUCLEI, HEAVY NUCLEI, ISOMERIC TRANSITION ISOTOPES, ISOTOPE ENRICHED MATERIALS, ISOTOPE SEPARATION, ISOTOPES, METALS, MINUTES LIVING RADIOISOTOPES, NUCLEI, RADIOISOTOPES, SEPARATION PROCESSES, URANIUM, URANIUM ISOTOPES, YEARS LIVING RADIOISOTOPES
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Radioaktivni odpady
Primary Subject
Secondary Subject
Source
1971; 154 p; Academia; Prague
Record Type
Book
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Specific problems are discussed encountered in fast reactor fuel reprocessing. A survey is given of the current state of art in fluoride reprocessing in different countries and studies conducted in Czechoslovakia in this field are summed up. (author)
Original Title
Fluoridove zpracovani vyhoreleho paliva rychlych reaktoru
Primary Subject
Record Type
Journal Article
Journal
Jaderna Energie; ISSN 0448-116X; ; v. 26(5); p. 189-190
Country of publication
BREEDER REACTORS, CZECHOSLOVAK ORGANIZATIONS, DOCUMENT TYPES, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, EXTRACTIVE METALLURGY, FAST REACTORS, FBR TYPE REACTORS, FUEL ELEMENTS, LIQUID METAL COOLED REACTORS, METALLURGY, NATIONAL ORGANIZATIONS, PLUTONIUM REACTORS, POWER REACTORS, PYROMETALLURGY, REACTOR COMPONENTS, REACTORS, REPROCESSING, RESEARCH AND TEST REACTORS, SEPARATION PROCESSES, SODIUM COOLED REACTORS, TEST REACTORS
Reference NumberReference Number
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AbstractAbstract
[en] In solutions containing uranium and zirconium salts the concentration of sulfuric acid is adjusted to 30 to 50%. Zirconium forms crystals of zirconium sulfate tetrahydrate while uranium remains in the substrate. (H.S.)
Original Title
Zpusob cisteni zirkoniovych soli od uranu krystalizaci z prostredi kyseliny sirove
Primary Subject
Source
15 Apr 1981; 2 p; CS PATENT DOCUMENT 187528/B/
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A method is proposed of accelerating hydrolysis of zirconium carbonate complexes from solutions containing carbonate and sulfate mixtures. The solutions containing 0.05 to 2 mol/l carbonates and 0 to 2 mol/l sulfates are heated for 1 to 60 minutes to a temperature of 100 to 250 degC. Zirconium changes into a precipitate insoluble in the mother liquor and the precipitate is then separated. The method allows obtaining pure zirconium as it can be separated from other elements forming carbonate complexes, such as uranium. The mother liquor can be regenerated. (A.K.)
Original Title
Zpusob urychleni hydrolyzy zirkoniovych uhlicitanovych komplexu
Primary Subject
Source
15 Nov 1986; 12 Dec 1983; 2 p; CS PATENT DOCUMENT 235647/B/; CS PATENT APPLICATION PV 9306-83; English translation available from Nuclear Information Center, 156 16 Prague 5-Zbraslav, Czechoslovakia at US$ 10 per page.; Application date: 12 Dec 1983
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A prototype was designed and built of a sodium aerosol indicator suitable for detecting possible leaks of sodium from experimental facilities. The indicator using the flame photometry principle is designed for continuous operation and requires minimal maintenance. The indicator essentially consists of a flue chamber where sodium particles are heated to the desired temperature. The chamber casing accommodates all connection instruments and an optical system including a photomultiplier. The combustion chamber with a hydrogen burner is housed inside the casing. The flame light concentrated by a hollow mirror and a double condenser to the photomultiplier photocathode passes through a double interference filter. In testing, a measurement error was found due to underpressure changes in the combustion chamber, voltage instability at the photomultiplier and hydrogen pressure instability. The resulting measurement error, however, does not exceed 8%. (Z.M.)
Original Title
Indikace koncentrace aerosolu sodiku
Source
Vesely, V. (ed.); Ceskoslovenska Komise pro Atomovou Energii, Rez (Czechoslovakia); p. 251-259; 1976; p. 251-259; Nuclear Information Centre of the Czechoslovak Atomic Energy Commission; Prague, Czechoslovakia; Scientific and technical conference commemorating the 20. anniversary of the Nuclear Research Institute's foundation; Rez, Czechoslovakia; 10 - 12 Jun 1975
Record Type
Miscellaneous
Literature Type
Conference
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Reference NumberReference Number
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