Journal of Nuclear Science and Technology
Online ISSN : 1881-1248
Print ISSN : 0022-3131
Volume 1, Issue 5
Displaying 1-5 of 5 articles from this issue
  • Electric Field Distortion due to Hall Effect
    Itaru MICHIYOSHI, Kunihiko UEMATSU, Masahiro NUMANO
    1964 Volume 1 Issue 5 Pages 147-154
    Published: 1964
    Released on J-STAGE: February 28, 2008
    JOURNAL FREE ACCESS
    This paper deals with an analysis of the current and electric field distributions in the entrance and exit regions of a linear MHD power generator, for the case where the working fluid (gas) exhibits the Hall effect. For simplicity, the following assumptions are adopted:
    (1) The MHD power generator is of constant-velocity-type.
    (2) The problem is two dimensional.
    (3) The electrical conductivity and the Hall parameter of the fluid and the magnetic field are constant and uniform in the region of interest.
    (4) The seeding material is injected uniformly at the entrance plane.
    Solutions are presented in closed form for several values of the Hall parameter, ωτ They show that the electric potential in the entrance plane assumes an extreme value between the electrodes, and that the length of the "entrance region" is of the same order as the distance between the electrodes. The influence of electric field distortion at the entrance on the current and electric field distributions is negligible beyond this region. The electric field distortion occurs in the exit region also, resulting in "end loss" which is approximately proportional to σeμ ωτ.
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  • Kenju WATANABE
    1964 Volume 1 Issue 5 Pages 155-162
    Published: 1964
    Released on J-STAGE: February 28, 2008
    JOURNAL FREE ACCESS
    The extraction of thorium and uranium chlorides by TBP and TOPO was studied. The composition of complexes extracted from the chloride solutions of low acid concentration was established by partition study to be UO2Cl2(TOPO)2, UCl4(TOPO)2, ThCl4(TOPO)2 and UCl4(TBP)2. Composition of the thorium complex in the TBP phase free from hydrochloric acid was revealed by infrared study to be ThCl4(TBP)4. The extraction behavior of thorium chloride by TBP was different from that of U(IV) and Pu(IV) chloride, and the composition of the complex was presumed to be HThCl5(TBP)4 in the extraction from concentrated chloride solution containing hydrochloric acid.
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  • Masao TAKIGISHI
    1964 Volume 1 Issue 5 Pages 163-171
    Published: 1964
    Released on J-STAGE: February 28, 2008
    JOURNAL FREE ACCESS
    A mathematical treatment to the optimum flow ratio for the counter-current extraction of penta and tetra complexes of nitrosylruthenium in the primary separation plant of reactor fuel processing has been developed from the previous publication(1)(2).
    The optimum flow ratio is a rather simple function of ratio of reaction rate constants and molar ratio of trinitrato complex to penta and tetra complexes.
    Another, and much higher, volume flow ratio for the maximum decontamination factor of penta and tetra complexes has also been numerically introduced for justification of the optimum flow ratio.
    The significant effect of lower nitric acidities in aqueous phase on the ruthenium decontamination has been discussed.
    Calculated results from the obtained equation for the optimum flow ratio have been compared with the values used in practice in the ruthenium decontamination process, and have shown remarkable agreement.
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  • Renzo TAKEDA, Kazuhiko INOUE
    1964 Volume 1 Issue 5 Pages 172-176
    Published: 1964
    Released on J-STAGE: February 28, 2008
    JOURNAL FREE ACCESS
    The effective cutoff energies for cylindrical detectors with cylindrical filters in isotropic neutron flux were studied. The reactor spectra used in calculating the effective cutoff energy were those for infinite homogeneous media using the free gas model of deuterium and carbon. The values of the effective cutoff energies for cylindrical geometry in isotropic neutron flux are intermediate between those in isotropic and beam neutron fluxes for slab geometry. Change of detector position in the filter considerably influences the value of the effective cutoff energy. The self-shielding effect is negligibly small in micro counters.
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  • Preparation of Cu-67
    Eiji SHIKATA
    1964 Volume 1 Issue 5 Pages 177-180
    Published: 1964
    Released on J-STAGE: February 28, 2008
    JOURNAL FREE ACCESS
    Copper-67, the longest-lived radioisotope of copper, was prepared by using the reaction 67Zn(n, p)67Cu. Zinc enriched in 67Zn up to 93.4% was irradiated in JRR-1 reactor for 5 hr with a fast neutron flux of 1.5×1012 n/cm2/sec. Copper-67 formed in the zinc target was separated by anion exchange separation using the chioro-complex of the metals. The yield of 67Cu and radiochemical impurity were investigated. Seventeen millimicrocuries of 67Cu was obtained from 1 mg of zinc. No radioactive impurities other than 64Cu were not found. Even with the use of enriched target, a more 64Cu was produced than 67Cu. The proportion of 67Cu to total copper radioactivity was 26% immediately after the irradiation
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