Journal of Nuclear Science and Technology
Online ISSN : 1881-1248
Print ISSN : 0022-3131
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Volume 5, Issue 3
Displaying 1-13 of 13 articles from this issue
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  • Theoretical Remarks on the Contribution of Chemical Reactions to Isotope Separation
    Hidetake KAKIHANA, Kimiko TAKAHASHI, Yumio YATO
    1968 Volume 5 Issue 3 Pages 93-97
    Published: March 25, 1968
    Released on J-STAGE: April 18, 2008
    DOIhttps://doi.org/10.3327/jnst.5.93
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    Fundamental equations for the isotopic separation factor are derived with consideration given to the role of chemical reactions. It is shown that the separation factor of isotopes can be devided into three terms, the isotope effects : (1) caused by the transfer of the species from the first to the second phase, (2) due to chemical reactions in the first phase, and (3) in the second phase. The first effect further consists of three terms, the isotope effects : caused (1) by the pure physical trans-fer of isotopic species, (2) by the hydration and solvation in the first phase and (3) in the second phase. A discussion is given on the use of the above equation in seeking combinations of chemical systems that provide for better separation of isotopes.
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  • Gamma-Ray Scattering from Point Sources by Infinite Plane Surfaces
    Mitsuyuki KITAZUME
    1968 Volume 5 Issue 3 Pages 98-103
    Published: March 25, 1968
    Released on J-STAGE: April 18, 2008
    DOIhttps://doi.org/10.3327/jnst.5.98
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    A method of evaluating the γ-dose rate resulting from a point source and scattered by a semi-infinite plane surface has been developed in the form of a single scattering formula. In this formula, the effect of multiple reflection within the medium is incorporated as buildup factor for the reflected γ-rays.
    Results of calculation with this formula are compared with values based on a semi-empirical ex-pression using the differential dose albedo of a semi-infinite concrete expanse, and with experimental values obtained on dose rates of γ-rays reflected by concrete and lead surfaces from point sources of 60Co (1.25 MeV), 137Cs (0.66 MeV) and 192Ir (0.4 MeV).
    It is seen that the results of the calculation agree fairly well with the experimental results.
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  • Studies on Cation Exchange Equilibria for the Uranyl-Hydrogen System
    Zenzi HAGIWARA, Ken-ichi OCHIAI
    1968 Volume 5 Issue 3 Pages 104-110
    Published: March 25, 1968
    Released on J-STAGE: April 18, 2008
    DOIhttps://doi.org/10.3327/jnst.5.104
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    Selectivity coefficients of the uranyl-hydrogen ion exchange system have been determined in a series of sulfonated polystyrene type cation exchange resins in three different degrees of crosslinkage at four different temperatures. The standard free energies of exchange ΔG° and the heats of ex-change ΔH were also estimated from the data of selectivity coefficients determined on the same resins. In general, the selectivity coefficient increased with both crosslinkage and temperature, and decreased with increasing proportion of uranyl in the resin phase. The study was further extended to the ex-change system of uranyl-ammonium in order to ascertain the validity of the magnitudes of selectivity coefficients obtained for the uranyl-hydrogen system. Good results were obtained on the exchange equilibria.
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  • Uranium Dioxide from Uranyl Nitrate-Tri-n-Butyl Phosphate Solution
    Tomitaro ISHIMORI, Eiko AKATSU, Michiko KAWASAKI, Kaoru UENO
    1968 Volume 5 Issue 3 Pages 111-116
    Published: March 25, 1968
    Released on J-STAGE: April 18, 2008
    DOIhttps://doi.org/10.3327/jnst.5.111
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    Uranium in uranyl nitrate-TBP solution was converted into dioxide by vacuum distillation and ignition. In vacuum distillation, TBP and its diluent were recovered at 40°150°C in nitrogen stream under 15mmHg. The residue of distillation was incinerated in nitrogen stream with 0.11.0mmHg by raising the temperature from 400° to 1, 300°C. The final product is a black powder of UO2, identified by X-ray diffraction, by density measurement and by chemical analyses. Uranyl nitrate TBP solution is evolved during fuel reprocessing, and thus the vacuum distillation reported here could be applied to the solution in order to simplify the process.
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  • Heat Transfer and Critical Heat Flux in Transient Boiling, (I)
    An Experimental Study in Saturated Pool Boiling
    Fujio TACHIBANA, Mamoru AKIYAMA, Hiroshi KAWAMURA
    1968 Volume 5 Issue 3 Pages 117-126
    Published: March 25, 1968
    Released on J-STAGE: April 18, 2008
    DOIhttps://doi.org/10.3327/jnst.5.117
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    Heat transfer and critical heat flux in saturated pool boiling were experimentally studied under transient power condition. The heating elements were flat plates of nickel submerged facing vertically in stagnant water. The heat generation rate in the test section was increased linearly in time, upon which, under certain conditions, the heat flux was found to reach a maximum point located in the nucleate boiling regime. The heat flux of this critical point increased with mounting sharpness of the transient, and the mechanism that occurs such a high critical heat flux may be the rapid formation and evaporation of thin liquid film at the bases of vapor bubbles. Examination of high speed motion pictures reveals that all bubbles on the heating surface are still in the phase of the first generation until the critical con-dition is reached. Compared to the case of steady boiling, the effect of differences in the heat capacity of the test section upon the critical heat flux was found to be less marked under the present experiment-al conditions.
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  • Gas Chromatography of Uranium Hexafluoride at Low Temperatures
    Shigeo TSUJIMURA, Ginji FUJISAWA, Hiroshi ITO
    1968 Volume 5 Issue 3 Pages 127-131
    Published: March 25, 1968
    Released on J-STAGE: April 18, 2008
    DOIhttps://doi.org/10.3327/jnst.5.127
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    Gas chromatography of UF6 at low temperature was studied with the use of columns of polytri-fluoromonochloroethylene oils as liquid phase.The dependence of retention time and HETP of UF6 on (1) degree of polymerization of oils, (2) liquid phase loading, and (3) kinds of solid support were studied in the temperature range between •10° and 40°C, and the most favorable conditions for quantitative analysis of UF6 are discussed.
    The relation between the gas chromatographic characteristics of the columns and the B.E.T.surface area of the solid support has been briefly examined.
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  • Errata
    1968 Volume 5 Issue 3 Pages 131b
    Published: 1968
    Released on J-STAGE: April 18, 2008
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  • Errata
    1968 Volume 5 Issue 3 Pages 131a
    Published: 1968
    Released on J-STAGE: April 18, 2008
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  • Comments on "On Neutron Wave Propagation Experiments in Graphite, by M. Utsuro and T. Shibata"
    Feroz AHMED, P.S. GROVER
    1968 Volume 5 Issue 3 Pages 132
    Published: March 25, 1968
    Released on J-STAGE: April 18, 2008
    DOIhttps://doi.org/10.3327/jnst.5.132
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  • Incipient Boiling on Exponentially Heated Surfaces
    Fujio TACHIBANA, Mamoru AKIYAMA, Hiroaki KAWASHIMA
    1968 Volume 5 Issue 3 Pages 133-135
    Published: March 25, 1968
    Released on J-STAGE: April 18, 2008
    DOIhttps://doi.org/10.3327/jnst.5.133
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  • Bubble Growth Rate in Transient Boiling
    Mamoru AKIYAMA, Fujio TACHIBANA, Hiroaki KAWASHIMA
    1968 Volume 5 Issue 3 Pages 135-136
    Published: March 25, 1968
    Released on J-STAGE: April 18, 2008
    DOIhttps://doi.org/10.3327/jnst.5.135
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  • Some Investigations of the Effect of "Bragg Continuum" on Wave Propagation Experiments in Graphite
    Akito TAKAHASHI, Kenji SUMITA
    1968 Volume 5 Issue 3 Pages 137-140
    Published: March 25, 1968
    Released on J-STAGE: April 18, 2008
    DOIhttps://doi.org/10.3327/jnst.5.137
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  • SN Ratio in the Rossi-α Experiment
    Nobuhiro YAMAMURO, Gohzoh INABA
    1968 Volume 5 Issue 3 Pages 140-141
    Published: March 25, 1968
    Released on J-STAGE: April 18, 2008
    DOIhttps://doi.org/10.3327/jnst.5.140
    JOURNAL FREE ACCESS
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