Journal of Nuclear Science and Technology
Online ISSN : 1881-1248
Print ISSN : 0022-3131
Volume 6, Issue 9
Displaying 1-12 of 12 articles from this issue
  • Itsuro KIMURA, Katsuhei KOBAYASHI, Toshikazu SHIBATA
    1969 Volume 6 Issue 9 Pages 485-493
    Published: September 25, 1969
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
    Making use of monoenergetic neutrons produced by a 2 MeV Van de Graaff accelerator, the cross section for the 103Rh(n, n')103mRh reaction was measured in the energy range from 180 keV to 4.6 MeV. To obtain the relative activity of Rh, the 2103m0keV X-rays emitted by the nuclide were measured with a thin NaI(Tl) scintillator with Be window. For absolute measurement, a standard 103Ru source was made from ruthenium trichloride irradiated with thermal neutrons. The self-shielding effect to the 20 keV X-rays was eliminated by the realization of a thin layer of Ru obtained by electrodeposition.
    The fission-spectrum-averaged cross section for this reaction determined by the present method is 558±32 mb, and the effective cross section 960±55mb.
    The reaction was applied to the measurement of the fast neutron flux in the experimental facilities of the Kyoto University Reactor. The present report also gives a discussion on the ad-vantage of using the 103Rh(n, n')103mRh reaction as fast neutron radiation damage monitor.
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  • Masayuki NAGAI, Toshio KAWAI, Masae HORI
    1969 Volume 6 Issue 9 Pages 494-497
    Published: September 25, 1969
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
    Transient characteristics of average temperature and heat flux of UO2 fuel rods have been obtained with account taken of the effect of temperature dependence of thermal properties. The first order deviation of the temperature distribution inside the fuel rod is solved by modal expan-sion, and the coefficients and time constants obtained for the transfer functions. The results have been compared with those by the conventional method: the differences found as a result in the transfer functions for typical fuel rods are within 1 dB in gain and 5 degrees in phase when the volume-averaged fuel temperature is used in the conventional method.
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  • Otohiko AIZAWA
    1969 Volume 6 Issue 9 Pages 498-507
    Published: September 25, 1969
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
    A series of reactivity measurements has been performed in a subcritical assembly using pulsed neutron source. The study is aimed at gaining information on the differences in the neutron population decay curve caused by differences in energy response of the detector used in the measurement. A discussion is given on the effective difference brought upon neutron spectra and in turn upon detector response due to the fact that the prompt flux is observed in decaying state and the delayed flux in nearly steady state. A scheme is proposed for compensating this difference in observed neutron fluxes. Comparison with experimental results is given, showing that, by means of the proposed correction, the calculated reactivity can be made independent of both detector position and detector type. To obtain meaningful values of reactivity without making use of this spectral correction, detectors with only epi-thermal response should preferably be used, which should be installed in the reflector region.
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  • Zenzi HAGIWARA
    1969 Volume 6 Issue 9 Pages 508-513
    Published: September 25, 1969
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
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  • Tsutomu HOSHINO
    1969 Volume 6 Issue 9 Pages 514-521
    Published: September 25, 1969
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
    The thermalization of pulsed neutrons has been numerically calculated with the application of the few-pole expansion method, which gives an approximate solution in the form of a super-position of pseudo modes (functions of energy) with pseudo decay constants (also functions of energy). The time dependent neutron flux, the Cd and Gd 7-activation responses, as well as the neutron temperature in a pulsed water assembly have been obtained as examples, and the results compared with experimental data, with calculations by direct time integration method, and with calculated time eigenvalues of the medium.
    These examples attest to the efficacy of the few-pole expansion method, the adoption of only three pseudo modes having yielded accurate numerical solutions, with only a small fraction of the computing time required by other methods such as direct time integration.
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  • Kazuo WATARI, Kiyoko IMAI, Masami IZAWA
    1969 Volume 6 Issue 9 Pages 522-525
    Published: September 25, 1969
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
    This report discusses the preparation of a number of metal salt-ion exchange resins and their application to radiochemical separation.
    The resins prepared by the subject method have properties of both metal salt and ion exchange resin.
    The present report describes the preparation and application of multi-loaded metal salt-ion exchange resin which contain one or more kinds of insoluble metal salt in an ion exchange resin, for which the residual ion exchange ability of an intermediate metal salt-ion exchange resin is utilized.
    The properties of multi-loaded nickel ferrocyanide-anion exchange resin and nickel ferrocyanide•calcium phosphate-anion exchange resin are also discussed.
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  • Nobuki KAWASHIMA, Sigeru MORI
    1969 Volume 6 Issue 9 Pages 526-530
    Published: September 25, 1969
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
    A simple and reliable method of levitating current-carrying hoops of a quadrupole magnetic field for thermonuclear fusion devices is presented. The hoops are initially posed on three supports, which are then propelled downward by repulsive force generated in a magnetic coil fed from a capacitor bank, leaving the current carrying hoops gravitating in space for more than 10 msec. The reproducibility is perfect and no damage nor deformation has been sustained by the components even after repeated use. Some preliminary experiments on plasma injection with this device are described. A suggestion is also presented on another possible method of levitation which should permit weightless suspension in space for longer periods as required in thermo-nuclear reactors.
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  • Hirohiko ADACHI, Shosuke IMOTO
    1969 Volume 6 Issue 9 Pages 531-535
    Published: September 25, 1969
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
    The magnetic susceptibility and electrical resistivity of uranium phosphides and UP-ThP solid solutions were measured. All the uranium phosphides exhibited paramagnetism at room tempera-ture, and followed the Curie-Weiss law. The Neel point TN for UP2 and UP, and the Weiss constant θ were estimated. Ferromagnetic components made their appearance in UP2 and UP, in the temperature range below TN. With UP-ThP solid solutions, the changes according to com-position observed in the values of TN and θ indicated that UP is magnetically diluted by ThP, which latter compound is characterized by Pauli paramagnetism, and whose presence contributes to diminish the exchange interactions.
    The electrical resistivity of UP increased rather rapidly with temperature up to a point corresponding to TN beyond which the tendency changed sharply to a slightly negative coefficient. ThP showed a consistently low value of resistivity, were slowly rising with temperature, and that of UP-ThP solid solutions revealed a behavoir intermediate between those of UP and ThP.
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  • N.P. KALASHNIKOV, G. LONGO
    1969 Volume 6 Issue 9 Pages 536-539
    Published: September 25, 1969
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
    The solution of a neutron multiple scattering problem is obtained by using a quantal approach. The elastic isotropic scattering is considered in the approximation where the scattering length is much less than both the neutron mean free path and the average distance between nuclei. In the case of a finite thickness slab, the probability density of the neutron momenta as a function of the traversed depth and of the scattering cosine is written directly in quadratures without using the transport equation.
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  • Yoshihiko KANEKO
    1969 Volume 6 Issue 9 Pages 540-542
    Published: September 25, 1969
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
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  • Jitsuya HIROTA, Hideo KUROI
    1969 Volume 6 Issue 9 Pages 542-545
    Published: September 25, 1969
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
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  • Toshifumi MURATA, Kiyoshi INOUE, Tadao KOBAYASHI
    1969 Volume 6 Issue 9 Pages 545-547
    Published: September 25, 1969
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
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