Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
Online ISSN : 2186-5256
Print ISSN : 0004-7120
ISSN-L : 0004-7120
Volume 1, Issue 4
Displaying 1-8 of 8 articles from this issue
  • J. SHIMOKAWA, G. NISHIO
    1959 Volume 1 Issue 4 Pages 225-233
    Published: September 30, 1959
    Released on J-STAGE: February 12, 2009
    JOURNAL FREE ACCESS
    An electrolytic deionization apparatus in which spherical ion exchangers and permselective ion exchqnge membranes were included was made for the treatment of radioactive aqueous wastes.
    Firstly the general characteristics of the ion exchange-electrolytic equipment were discussed in comparison with the ion exchange column and the ion exchange membrane equipment.
    Secondly equations for the distribution of ion concentrations in the deionization cell of the apparatus were derived as a function of feed concentration, flow rate, electric voltage, current, current efficiency, equivalent conductivities of ion exchangers and solutions, volume fraction of particles and cell geometry.
    The radioactive 24Na tracers have been utilized to measure actual ion concentrations in the deionization cell.
    The agreement of results on the distribution of the ion concentrations is satisfactory, that on the capacity of the deionization cell much so.
    The experimental data for low solid wastes indicate that the electrolytic process incorporating resin particles and resin membranes is superior to the simple process using permselective membranes only.
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  • N. IKEDA, H. EBIHARA
    1959 Volume 1 Issue 4 Pages 234-239
    Published: September 30, 1959
    Released on J-STAGE: February 12, 2009
    JOURNAL FREE ACCESS
    Since Szilard and Chalmers prepared the carrier-free radiohalogens from the organohologen compouds in 1934, the Szilard-Chalmers method has been applied to the separation of radioisotopes in a high specific activity.
    In order to prepare silicon-31 and phosphorus-32 in a high specific activity, the authors investigated the process with tributyl phosphate as the target material.
    Tributyl phosphate was bombarded with neutron by the cyclotron (neutron flux: 107n/cm2.sec), and radioactive 31Si and 32P formed were extracted from tributyl phosphate with the various kinds of extracting reagents.
    The percentage yield of separated 31Si activity showed the maximum value 87.5% when potassium hydroxide-solution of pH 12.5 was used, while percentage yield of 32P showed the maximum value, 54.3%, in the same conditions.
    Both anion and cation exchange resins were tried for the separation of 31Si and 32P from each other, and the cation exchange resin, Diaion SK-1 (ferric form), gave the most preferable results. 31Si and 32P separated by the procedure mentioned above were almost in a carrier-free form, and rediochemical purity of 31Si was 99.9% and that of 32P was nearly 100.0%
    Thus, we could prepare the radioactive 31Si and 32P in a high specific activity and in a high radiochemical purity by a simple procedure in a short while.
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  • Z. TAKAO, M. NISHIHARA, Y. YAGI, K. MIYAMOTO
    1959 Volume 1 Issue 4 Pages 240-248
    Published: September 30, 1959
    Released on J-STAGE: February 12, 2009
    JOURNAL FREE ACCESS
    Zircaloy-2 and -3 are now most widely used for canning material of fuel elements as well as for structural material for various types of reactors. Therefore, study has been made to the establish the melting and fabrication technique of these alloys in this country and their properties has also been exammined. Using a newly designed and constructed vacuum arc melting furnace for the melting of zirconium alloys, ingots of Zircaloy-2 and -3 have been successfully produced by consumable electrode double arc melting method and sheets, bars, pipes and wires have been fabricated through hot and cold working such as forging, rolling, extrusion and drawing.
    On the other hand, method of spectrochemical analysis of alloying elements and hafnium in those alloys has also been developed. Beside this, various properties of the zirconium products; such as tensile properties, creep rupture properties, corrosion properties and so on have been studied. It is proved from these tests that the properties of thus made zirconium alloys is quite satisfactorily compared with that of foreign made alloys, which has given fundamental informations to produce zirconium alloys for reactor applications in an industrial scale in this country.
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  • M. KITAZUME, T. KAWAI, K. HASEGAWA
    1959 Volume 1 Issue 4 Pages 249-258
    Published: September 30, 1959
    Released on J-STAGE: February 12, 2009
    JOURNAL FREE ACCESS
    Wigner-Wilkins have analytically calculated the neutron spectrum in an infinitely large monatomic hydrogen gas moderator in which the absorption cross section has the usual inverse dependence on velocity, v.
    However, the above analytical methods cannot always be applicable. We have numerically calculated the neutron spectrum in a monatomic hydrogen gas moderator which contains hypothetically much amount of 239Pu absorber or 1/v law dependent absorber, using the following assumptions.
    (1) The temperature of the moderator T=581°K
    (2) The scattering cross section of hydrogen is constant (50 barn)
    (3) The ratio of the number of atoms of 239Pu or 1/v law absorber to the hydrogen atom are 0, 0.01 and 0.02. The absorption cross section are taken from the BNL-325 charts.
    When the moderator contains no 239Pu, the distribution of the neutron velocities is approximately in Maxwellian. However, when the concentration is 0.01 or 0.02, the spectrum is shifted in the direction of higher energies, that is the spectrum is hardened, but there is a pronounced dip at the 0.3 eV resonance of 239Pu. In the case of the 1/v law absorber, the distribution is Wigner-Wilkins spectrum, and the spectrum is only shifted in the direction of higher energies.
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  • K. KIDA, M. ABE, S. NISHIGAKI, S. IMURA
    1959 Volume 1 Issue 4 Pages 259-271
    Published: September 30, 1959
    Released on J-STAGE: February 12, 2009
    JOURNAL FREE ACCESS
    High grade powderd beryllia, obtained through decomposition of BeSO4 was used as the raw material, from which the beryllia powder compact with the density of 3.00g/cc was obtained (whereas theoretical density is 3.02g/cc). The densification has been accomplished through hot pressing in a graphite mould and the heating by induction for 30min at 1, 400°C has been performed under the pressure of 200kg/cm3 in vacuum of 10-3 mmHg.
    The main subject concerned was to find the best condition for the vacuum hot pressing of beryllia, and the chcracteristics of thus-prepared beryllia has been studied as well.
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  • W. Herbert Pennington
    1959 Volume 1 Issue 4 Pages 272-282
    Published: September 30, 1959
    Released on J-STAGE: February 12, 2009
    JOURNAL FREE ACCESS
  • 1959 Volume 1 Issue 4 Pages 283-285
    Published: September 30, 1959
    Released on J-STAGE: February 12, 2009
    JOURNAL FREE ACCESS
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  • 1959 Volume 1 Issue 4 Pages 285
    Published: 1959
    Released on J-STAGE: February 12, 2009
    JOURNAL FREE ACCESS
    Download PDF (426K)
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