日本原子力学会誌
Online ISSN : 2186-5256
Print ISSN : 0004-7120
ISSN-L : 0004-7120
2 巻, 6 号
選択された号の論文の9件中1~9を表示しています
  • ポーラログラフ法
    本島 健次, 岡下 宏, 勝山 和夫
    1960 年 2 巻 6 号 p. 313-316
    発行日: 1960/06/30
    公開日: 2009/02/12
    ジャーナル フリー
    An analytical method is proposed for the polarographic determination of uranium (VI) in uranium tetrafluoride samples.
    A sample weighing about 500mg is treated with 20ml of 0.1M NaF solution using a magnetic stirrer, and is subjected to centrifugation. Two milliliters of the supernatant solution and 5ml of supporting electrolyte solution (1.3M HOAc+0.7M NH4OAc+0.2M BeSO4) are taken into a 10-ml volumetric flask and the resulting solution is diluted to the mark with water. Uranium (VI) in the solution is determined polarographically by referring to the standard calibration curve.
    For the purpose of suppressing the dissolution of uranium (IV) into the solution, NaF is used at the time of the sample digestion. The acetate buffer solution keeps the pH of the solution at 5 and Be2+ ion removes the interference of F- ion in the polarographic measurements. Instead of Be2+, Al3+ can be used for the same purpose.
    By this method as small as 0.05% of uranium (VI) in uranium tetrafluoride can be readily determined.
  • 浜口 博, 黒田 六郎, 細原 匡一
    1960 年 2 巻 6 号 p. 317-320
    発行日: 1960/06/30
    公開日: 2009/03/27
    ジャーナル フリー
    The mercury, copper and arsenic contents of some marine organisms have been determined by neutron activation. The irradiations were carried out in JRR-1 reactor, with neutron fluxes of about 3×1011 n/cm2/sec, and the irradiation lasted 23 days (intermittently, 5hr each day). After cooling for 2 days the sample was dissolved by treating with nitric-sulfuric acid and potassium permanganate in the presence of carriers. From the clear solution the mixed sulfides were separated from the bulk of the contaminating activities, and the arsenic and copper was dissolved out by treating successively with hot 6 N ammonium polysulfide and 6 N nitric acid, leaving the mercury sulfide unattacked. Further decontamination chemistry was carried out for each element. The amount of the element in the marine organisms was then determined by comparing 203Hg, 64Cu and 76As β-activities isolated from the sample with those from the monitor.
    The mean chemical yield was 40, 65 and 30% for mercury, copper and arsenic respectively, and the sensitivity of the method was Hg 1.5μg, Cu 0.03μg and As 0.04μg. The method has an advantage in that it makes possible to minimize the loss and contamination, which are the greatest obstacle in other analytical techniques for the determination of extremely minute amounts of these elements.
  • 藤崎 幸雄, 福井 資夫, 香川 達雄, 相波 哲朗
    1960 年 2 巻 6 号 p. 321-327
    発行日: 1960/06/30
    公開日: 2009/02/12
    ジャーナル フリー
    It is an important problem for the design of boiling water reactors to evaluate the pressure drop in two-phase flow of liquid and vapor.
    Experimental results are described about the pressure drop of steam-water mixture flowing at normal pressure in vertical circular tubes, annuli, bent and orifice. It is shown that:
    The ratio of the pressure drop of two-phase flow in annular spaces to that of single phase flow in them is nearly the same with the case of circular tubes, and depends only on the quality, but not on the mass velocity.
    When an orifice is used for measuring the velocity of fluid containing a few percentage of its own vapor, the error introduced for the estimation of velocity becomes fairly large, unless some modification is applied to the usual equation for single phase flow.
  • 木村 健二郎, 石森 富太郎, 内藤 奎爾, 梅沢 弘一, 渡辺 賢寿
    1960 年 2 巻 6 号 p. 328-336
    発行日: 1960/06/30
    公開日: 2009/03/27
    ジャーナル フリー
    Natural or depleted uranium targets were irradiated in JRR-1 with 1011n/sec⋅cm2 flux for 3060hr. After setting the irradiated target aside for a few months in a hot-cave, 239Pu was isolated by TBP solvent extraction method from bulk of uranium and the fission products and then purified by an anion-exchange method.
    It was found that 239Pu thus obtained was not contaminated with uranium and 210Po. However, it contained β, γ-activity of about 30 days half-life slightly.
  • 原子炉内流動水腐食試験装置
    野村 末雄
    1960 年 2 巻 6 号 p. 337-342
    発行日: 1960/06/30
    公開日: 2009/02/12
    ジャーナル フリー
    For the purpose of getting informations on the corrosion behavior of aluminium in aqueous system under pile irradiation as well as on the techniques of in-pile loop experiment, a simple in-pile corrosion test loop was designed and placed in No.9 beam hole at JRR-1 reactor, which has been operated under the following condition close to what will be encountered by the fuel cladding aluminium in JRR-3 reactor now under construction, except thermal neutron flux density.
    Temperature: Room temp. up to 100°C
    Flow rate: max. 3m/sec
    Thermal neutron: max. ca. 3×1011 n/cm2. sec
    The most part of this loop was made of 18-8 stainless steel (AISI type 304) and the aluminium test specimens are designed to be placed at various positions in the test section within the reactor. Neutron flux distribution has been measured from induced activities in test specimens placed at various positions in the test section of the loop.
  • 山田 太三郎, 青木 敏男
    1960 年 2 巻 6 号 p. 343-352
    発行日: 1960/06/30
    公開日: 2009/03/27
    ジャーナル フリー
    The application of the digital computer in nuclear engineering has been increasing rapidly, and many scientists and engineers are engaged in this field. In order to coordinate their activities, the Japan Nuclear Codes Group (JNCG) and the Shielding Codes Group (SCG) were organized in the middle of 1959. The following paper describing the historical and present status was prepared by these groups and presented at Seminar on Codes for Reactor Computation at Vienna, Austria (April 2529, 1960), sponcered by International Atomic Energy Agency (IAEA).
    For the editorial convenience, the Lists of the Registered Codes will be presented in the next number of this Journal
    The editoiral staffs of this compilation were:
    K. Arai (HITACHI) K. Ono (CRIEPI)
    Y. Arai (JAPCO) M. Takada (TOKYO UNIV.)
    M. Hachiya (MITSUI) T. Takeshita (IBMJ)
    T. Kawai (HITACHI) S. Terasawa (HITACHI)
    T. Morita (ETL) M. Tokizawa (NAIG)
    T. Nakayama (JAERI) A. Tsuruo (KAJIMA)
  • 1960 年 2 巻 6 号 p. 353-355
    発行日: 1960/06/30
    公開日: 2009/02/12
    ジャーナル フリー
  • 1960 年 2 巻 6 号 p. 355
    発行日: 1960年
    公開日: 2009/02/12
    ジャーナル フリー
  • 1960 年 2 巻 6 号 p. 356-366
    発行日: 1960/06/30
    公開日: 2009/02/12
    ジャーナル フリー
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