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  • 1
    Electronic Resource
    Electronic Resource
    Authors' reply
    Amsterdam : Elsevier
    International Journal of Radiation Applications & Instrumentation. Part 38 (1987), S. 162 
    Details
    ISSN: 0883-2889
    Source: Elsevier Journal Backfiles on ScienceDirect 1907 - 2002
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1016/0883-2889(87)90016-5
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    Paper (German National Licenses)
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  • 2
    Electronic Resource
    Electronic Resource
    Neutron yields from actinide oxides
    Amsterdam : Elsevier
    International Journal of Radiation Applications & Instrumentation. Part 37 (1986), S. 121-125 
    Details
    ISSN: 0883-2889
    Source: Elsevier Journal Backfiles on ScienceDirect 1907 - 2002
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Type of Medium: Electronic Resource
    URL: http://linkinghub.elsevier.com/retrieve/pii/0883-2889(86)90058-4
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  • 3
    Electronic Resource
    Electronic Resource
    Extraction chromatography in the DHDECMP(XAD-4)-HNO3 system (1990)
    Springer
    Journal of radioanalytical and nuclear chemistry 140 (1990), S. 195-203 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract An organic resin impregnated with DHDECMP was prepared for extraction chromatography and used for separation of the actinide elements. A known amount of inert support, Amberlite XAD-4, was contacted with a given amount of the extractant and water. By contacting the three phases for several hours at room temperature, the resin can be modified regardless of its mesh size. It is loaded with (1.13±0.03) g of DHDECMP per 1 g of the support. A given amount of the modified resin was contacted 50 times with fresh 3M nitric acid solution to remove the loosely bound extractant from the support. its amount was less than 1 weight%. As an application,241Am was recovered from 3.5M nitric acid waste solution on a column of the modified resin. Decontamination factor for the effluent was 105, while approximately 113 mg of241Am was obtained in 0.3M nitric acid eluting solution with 95% efficiency.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02037377
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  • 4
    Electronic Resource
    Electronic Resource
    Extraction chromatography in the DHDECMP—HNO3 system (1991)
    Springer
    Journal of radioanalytical and nuclear chemistry 149 (1991), S. 13-23 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract The extraction behaviour of Ce(III) and Am(III) in extraction chromatography has been investigated on the basis of partition and infrared studies. The stationary phase was purified undiluted DHDECMP supported on Amberlite XAD-4 and the mobile phase was nitric acid. The results have shown that the equilibria for the extraction of Ce(III) and Am(III) by the DHDECMP/XAD-4 resin agreed very closely with those in solvent extraction.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02053708
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  • 5
    Electronic Resource
    Electronic Resource
    Extraction chromatography in the DHDECMP—HNO3 system (1991)
    Springer
    Journal of radioanalytical and nuclear chemistry 149 (1991), S. 25-34 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract The characteristics of the DHDECMP/XAD-4 resin on the separation of americium, curium, californium and fission products have been studied. The capacity of the DHDECMP/XAD-4 column was compared with the maximum capacity determined by batch experiment using cerium. On the other hand, the elution behaviour of the trivalent actinide elements and fission products was investigated by extraction chromatography in the DHDECMP—HNO3 system.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02053709
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  • 6
    Electronic Resource
    Electronic Resource
    Non-destructive determination of spontaneously fissioning nuclides by neutron coincidence counting using multichannel time spectroscopy (1988)
    Springer
    Journal of radioanalytical and nuclear chemistry 125 (1988), S. 29-40 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract A non-destructive method for determining the amount of actinoids has been developed. The method is based on thermal neutron coincidence counting and employs a selective detection of neutrons resulting from the spontaneous fission of actinoids. The detection system is described in detail and the measurement results of244Cm as an example are presented. The results show that the measured fission rate of244Cm is consistent with the fission rate calculated from ENDF/B-V data and that the amount of244Cm can be determined within about 5% accuracy even in the presence of a large amount of actinoids, for example, up to 2.6·106, 3.6·104, or 1.6·103 times in the mass ratio of239Pu,241Am, or240Pu to244Cm, respectively.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02041746
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  • 7
    Electronic Resource
    Electronic Resource
    Non-destructive determination of239Pu in wastes by application of γ-ray measurement (1984)
    Springer
    Journal of radioanalytical and nuclear chemistry 86 (1984), S. 159-169 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract Amounts of239Pu in alpha-bearing wastes were determined by γ-ray measurement using a NaI/Tl/ scintillation detector. The deviations of measurement caused by the nonuniform distribution of239Pu in the wastes and by a volume factor were corrected by rotating and scanning the objects. Contribution from241Am coexisting with239Pu was also corrected by taking into account the difference of the counts between A /356–470 keV/ and B /475–620 keV/ intervals. Attenuation of γ-ray of239Pu was estimated from the matrix density. Thus the content of239Pu could be determined within an accuracy of about 25% at the 1 mg level in a cardboard carton of 17 1.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02166888
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