日本原子力学会誌
Online ISSN : 2186-5256
Print ISSN : 0004-7120
ISSN-L : 0004-7120
7 巻, 12 号
選択された号の論文の6件中1~6を表示しています
  • 乱流速度分布
    岐美 格, 松本 隆一, 中井 優, 菊池 三郎
    1965 年 7 巻 12 号 p. 680-686
    発行日: 1965/12/30
    公開日: 2009/03/31
    ジャーナル フリー
    This report presents analyses on the velocity profile of turbulent flow of Bingham plastic fluid and on the eddy diffusivity for the momentum transport of such fluid. Experimental data on velocity profiles of alumina-water slurry obtained with Pitot tube are located roughly mid-way between the two theoretical velocity profiles usually known as the logarithmic and power velocity profiles, which were calculated by using the friction coefficient discussed in the preceding 2nd report.
    The ratio of eddy diffusivity to kinematic viscosity of slurry derived from the two theoretical velocity profiles increases with Reynolds and Hedström numbers. This however is applicable only in the range of Reynolds number from 1.5×104 to 3×104 with Hedström number less than 5×105.
  • 渡辺 斉
    1965 年 7 巻 12 号 p. 686-693
    発行日: 1965/12/30
    公開日: 2009/03/31
    ジャーナル フリー
    Metallographic structure, precipitation hardening, and distribution of precipitates were studied on γ-quenched U-Fe alloys containing from 400 to 900 ppm of Fe.
    Neither β nor γ phases was retained in specimens water-quenched from 800° or 850°C, and only the α phase was observed. During the subsequent annealing, hardening was found to occur in one or two steps, caused by the precipitation of U6Fe. This hardening appears to be similar in nature to that experienced with Al-Cu alloys. The size and number of precipitates in variously heat-treated specimens were measured by electron micrography. The results obtained are discussed, with particular reference to the effect of precipitates on swelling, and are compared with data from the Harwell group on the bubble density in α-U irradiated to 0.5 a/o burnup.
  • 喜多尾 憲助
    1965 年 7 巻 12 号 p. 694-702
    発行日: 1965/12/30
    公開日: 2009/03/31
    ジャーナル フリー
    The use of the nuclear reactor for biological and medical purposes especially in therapeutic applications, health physics research and radiobiological investigation, is summarized. The status of research work and utilization of these reactors is also presented.
    At present, the production of radioisotopes is the most important application of the reactor is biology and medicine. Most biological and medical reactors have only recently begun to be operated, so that prominent work with their we can hardlg be expected yet. If these reactors provide good operating results and granted the solution of a number of basic radiobiological problems, the neutron therapy and other biomedical applications have excellent prospects of success.
  • ジルコニウム合金水素吸収試験研究委員会
    1965 年 7 巻 12 号 p. 703-712
    発行日: 1965/12/30
    公開日: 2009/03/31
    ジャーナル フリー
    The effect of hydrogen on Zr alloys used for fuel cladding is a very important problem from the point of view of reactor safety. Three kinds of experiments were carried out, the results of which can be summarized as follows.
    (1) Corrosion test: This test was performed to clarify the relation between coolant water conditions and hydrogen pick-up. The factors considered were the composition of the alloys (Zircaloy-2 and -4), as well as the gas content (oxygen, hydrogen and flourine ion), pH, temperature and pressure of the water. Among these, the amount of flourine ion and temperature were found to be the only factors that have appreciable effect on hydrogen absorption.
    (2) Hydrogen distribution test: The effect of alloying elements (Be, V, Y and Nb) on hydrogen distribution in Zircaloy under temperature gradient was examined. The shift of the hydrogen peak was observed to be influenced in different ways according to the alloying element added.
    (3) Mechanical test: The effect of hydrogen content on the mechanical properties of the alloys was studied. In tensile test, no appreciable effect of hydrogen content up to 300ppm, was observed. In burst test also, little influence of absorbed hydrogen on the burst strength of Zircaloy-2 tubing was discerned, but severer cracking in the tubing as well as increasing tendency toward brittleness was apparent with increasing hydrogen content.
  • 1965 年 7 巻 12 号 p. 713-715
    発行日: 1965/12/30
    公開日: 2009/03/31
    ジャーナル フリー
  • 黒田 孝
    1965 年 7 巻 12 号 p. 716-719
    発行日: 1965/12/30
    公開日: 2009/03/31
    ジャーナル フリー
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