Journal of Nuclear Science and Technology
Online ISSN : 1881-1248
Print ISSN : 0022-3131
Volume 5, Issue 6
Displaying 1-12 of 12 articles from this issue
  • Masanobu SAKANOUE, Masataka MATSUURA, Masakatsu SAEKI
    1968 Volume 5 Issue 6 Pages 265-270
    Published: June 25, 1968
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
    The fast neutron flux in the central thimble of a TRIGA-II reactor was estimated by using the 238U(n, 2n)237U reaction as flux monitor. The thermal neutron flux also was estimated by 238U(n, γ)→239Np and 232Th(n, γ) →233Pa reactions. The latter flux was further measured at the same time by γ-ray spectrometry of the product nuclides and by chemical separation and β counting with α emitting isotopes as tracer. The values of flux thus obtained were compared with those estimated from the amounts of 28Al, 27Mg and 24Na respectively produced by the (n, γ), (n, p) and (n, α) reactions on 27Al. Furthermore, for the first time, the effective cross section for the 238U(n, 2n)237U reaction was estimated to be 2.8b from a comparison with that for the 27Al(n, α)24Na reaction.
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  • Nobuhide SUDA
    1968 Volume 5 Issue 6 Pages 271-278
    Published: June 25, 1968
    Released on J-STAGE: April 18, 2008
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    As a prerequisite to the optimal control of the neutron flux distribution of large reactors, the controllability of the flux distribution is invenstigated. The distributed parameter system is reduced to a lumped parameter system by means of truncated modal expansion. In a one dimensional reactor, any number of modes are controllable by a single control rod. To maintain the amplitude of each mode at a prescribed level however, it is necessary to have as many control rods as the number of the modes. Discussions are also presented on the decomposition of the optimal control of fiux distribution into those of the individual modes, on the controllability of reactors with feedback, and on the controllability when there is constraint on the control rod speed.
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  • Mitsuyuki KITAZUME
    1968 Volume 5 Issue 6 Pages 279-286
    Published: June 25, 1968
    Released on J-STAGE: April 18, 2008
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    Leakage radiation from an infinite plane source reaching the rear surface of a shield provided with an annular duct has been evaluated numerically. The plane of the infinite source is divided into eight zones, for the convenience of integration, and the contribution of each zone is calculated separately by ray analysis. The distribution of the radiation flux and dose rate around the duct have been systematically obtained for different shielding materials and source energies, and the effect of changing duct geometry is also analyzed.
    changing duct geometry is also analyzed.Among the contributions from the different zones, it is found that the predominant portion is provided by zones outside the annular area, and that this predominance extends even to the region of shield surface directly above the duct. It is also demonstrated that Rockwell's expression based on Line-of-Sight method is included as a special case of the present formula, which is applicable not only to γ-rays, but also to fast neutrons.
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  • Tetsuo INADA
    1968 Volume 5 Issue 6 Pages 287-291
    Published: June 25, 1968
    Released on J-STAGE: April 18, 2008
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    An attempt has been made of using Nal(Tl) crystal as fast neutron detector in conventional Time-of-flight apparatus. Typical pulse hight distributions, in the γ-ray energy range below 1 MeV, produced by the incidence of fast neutrons are presented. The characteristics of this neutron detection system have been studied, using pulsed neutrons from the T(p, n) and D(d, n) reactions. Neutron detection efficiency curves are presented, covering both whole γ-rays and those from a few low excited levels of 127I nucleus. The detection bias can be stably set at the first excitation energy (58keV), which is lower than possible for an organic scintillator.
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  • Bumpei ISHII, Shuichiro TAKAHASHI
    1968 Volume 5 Issue 6 Pages 292-297
    Published: June 25, 1968
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
    A study was made of the microstructure of swaged UO2, irradiated to a burnup of 3, 000 MWD/T-U at an estimated center-line temperature of 1, 400°C.
    In the peripheral zones of the specimen near the cladding, evidence was observed of sintering of the UO2 particles by irradiation even at comparatively low temperatures (about 300°400°C). Tracks of fission product fragments were observed at the inner wall surface of cracks in the specimen. The width of the tracks is seen to be larger than observed on thin films and on sintered UO2. Mixed phases of UO2 and fission products precipitated in the interior of crystal grains, observed in the form of hillocks left unetched, were surmounted by several sprouts of substances still more chemically stable. Mixed phases of UO2 and fission products were precipitated on the inner wall surface of the cracks and appeared upon etching as stepped protuberances of irregular contours. A comparison between the microstructures of swaged UO2 and sintered UO2 irradiated under the similar conditions is discussed.
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  • Masahiko UTSURO, Kazuhiko INOUE, Toshikazu SHIBATA
    1968 Volume 5 Issue 6 Pages 298-308
    Published: June 25, 1968
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
    Theoretical and experimental studies concerning the effects of Bragg cut-off on the neutron wave propagation in graphite are presented, as analyzed from the two following factors related to the Bragg cut-off.
    First, the inordinately long mean free path of cold neutrons of energies below the Bragg cut-off causes in some cases serious problems due to the deep penetration and the strong leakage of the cold neutrons.
    Secondly, the extremely low collision frequency of about 2, 500 rad/sec for the cold neutrons produces a "singular frequency" at a point of even lower frequency, wherein the waves do not decay exponentially in the propagating direction.
    The peculiar behavior of these cold neutrons severely restricts the conditions of experiment under which one can derive an exact value for the propagation parameter in graphite. In certain cases, however, one can obtain meaningful approximate information about wave propagation from experiments conducted beyond these limiting conditions, provided that certain precautions are taken in carrying out the experiment and in interpreting the results. Analysis to explain these phenomena and experiments to reveal the effects in graphite are described.
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  • Kazuo WATARI, Kiyoko IMAI, Masami IZAWA
    1968 Volume 5 Issue 6 Pages 309-312
    Published: June 25, 1968
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
    Preparation of iron ferrocyanide-anion exchange resin and adsorption of 137Cs on the resin are described.
    The resin was found to effectively adsorb 137Cs from concentrated nitric acid solution, contrast to the negative results previously obtained with copper ferrocyanide-anion exchange resin.
    A discussion is given of the possibility of applying the iron resin to the removal of 137Cs from fuel reprocessing waste solution.
    Fission products were effectively separated from each other with a column of this resin, utilizing the properties possessed by it of both iron ferrocyanide and the parent ion exchange resin.
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  • 1968 Volume 5 Issue 6 Pages 312a
    Published: 1968
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
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  • 1968 Volume 5 Issue 6 Pages 312b
    Published: 1968
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
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  • Akira DOI, Hiroshi HAYASHI, Yasuo OHSAWA, Kiyoshi INOUE
    1968 Volume 5 Issue 6 Pages 313-315
    Published: June 25, 1968
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
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  • Keiichi SAITO, Yukichi TAJI
    1968 Volume 5 Issue 6 Pages 315-317
    Published: June 25, 1968
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
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  • Shoichi NASU, Takeo KIKUCHI
    1968 Volume 5 Issue 6 Pages 318-319
    Published: June 25, 1968
    Released on J-STAGE: April 18, 2008
    JOURNAL FREE ACCESS
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