日本原子力学会誌
Online ISSN : 2186-5256
Print ISSN : 0004-7120
ISSN-L : 0004-7120
2 巻, 12 号
選択された号の論文の9件中1~9を表示しています
  • 八三酸化ウランの生成条件と化学反応活性との関係
    宇梶 六夫
    1960 年 2 巻 12 号 p. 731-735
    発行日: 1960/12/30
    公開日: 2009/02/12
    ジャーナル フリー
    The conditions of precipitating ammonium diuranate (ADU) and uranium peroxide (UPO) from uranyl nitrate (UNH), the temperature of thermal decomposition and the rate and duration of heating were studied in order to estimate the reactivity of uranouranic oxide, U3O8 I, II and III which was prepared from UNH, ADU and UPO.
    The results were as follows:
    (1) The concentration of uranyl ion, the addition speed of precipitant, the stirring condition, etc. had some effects on the specific surface area of U3O8 II and III, but almost no effects on the width of X-ray diffraction spectra of these oxides.
    (2) The high reactivity of U3O8 I prepared by rapid heating may be due to the formation of amorphous U3 I on the way of thermal decomposition of UNH.
    (3) The low chemical reactivity of U3O8 III prepared by very slow heating was also explained as the result of the formation of monoclinic crystalline U3 III.
  • 林 重憲, 岩住 哲朗, 若林 二郎, 桜井 彰, 青木 英人, 北村 元彦
    1960 年 2 巻 12 号 p. 736-741
    発行日: 1960/12/30
    公開日: 2009/03/27
    ジャーナル フリー
    In order to study the transient nucleate boiling on the fuel plate surface of a light water cooled and moderated reactor when a sudden large reactivity is given to it, the fundamental experiment have been made by means of steppd electrical heating of metal foil located in stagnant water under atmospheric pressure.
    From these studies, it is understood that the temperature overshoot of the metal surface from the saturation temperature of water and the delay time between passage of saturation temperature and the beginning of boiling, may, regardless of the degree of subcooling, be predicted in terms of the temperature rising velocity of the metal surface.
    With thase results, it is possible to make a precise analysis of the light water cooled and moderated reactor kinetics in case of the power excursion.
  • 解析方法および結果の概要
    三井田 純一, 須田 信英, 竹内 哲夫, 入江 敏雄
    1960 年 2 巻 12 号 p. 742-748
    発行日: 1960/12/30
    公開日: 2009/02/12
    ジャーナル フリー
    This and the subsequent reports are on the study by use of an analogue computer of the dynamic characteristics of a British type gas cooled reactor during its large power changes. It is assumed that power changes are caused by changing the cooling gas flow rate under the condition that the outlet gas temperature is kept constant by a temperature control system.
    This study is mainly concerned with the performances of the reactor with positive moderator temperature coefficient of reactivity, and it includes the investigation of the stability, the transient characteristics, the comparison of continuous and discontinuous controllers, and reactivity requirements for control rods, during large power changes.
    In this report (I) we describe the method of analysis and an outline of results, leaving the more specialized discussion of results and the conclusions to the report (II).
  • 石森 富太郎, 渡辺 賢寿, 木村 幹
    1960 年 2 巻 12 号 p. 750-757
    発行日: 1960/12/30
    公開日: 2009/03/27
    ジャーナル フリー
    酸化トリウムをJRR-1で173時間照射し,約5個月冷却したのち生成した233Uを,溶媒抽出法によりトリウムおよ.び233Paから分離し,イオン交換樹脂法により精製した。照射した酸化トリウムに,微量のフッ化カリウムを含む濃塩酸を加え,還流しながら加熱して溶解した。照射トリウムの4~6N塩酸溶液から, 1%トリブチルフオスフィンオキシドートルエン溶液で数回抽出を行なえば,トリウムは水相に残り233Paと233Uは有機相に移る。つぎにこの有機相をフッ化ナトリウムを飽和した4~6N塩酸溶液で数回洗う。フッ化ナトリウムを飽和した塩酸溶液と1%TBPOとの間の分配率は, Paでは塩酸のみからの抽出の場合に比べて著しく小となるが,ウランにおいてはなお比較的高い値を保つ。したがって数回洗うことによって233Paの大部分は水相に移るが, 233Uは有機相に残る。233Uの逆抽出は約4N酢酸で行なった。最後に233Uの酢酸溶液を0.02Mのフッ化ナトリウムを含む0.1N塩酸溶液に変えて陽イオン交換樹脂によって精製した。0.02Mフッ化ナトリウムー0.1N塩酸の約50mlで樹脂を洗えば233Paはほとんど除かれる。2N塩酸20mlにより233Uを溶離した。
    得られた試料はαスペクトロメトリーにより,エネルギーを測定し233Uであることを確かめた。
  • 三沢 英勝
    1960 年 2 巻 12 号 p. 758-766
    発行日: 1960/12/30
    公開日: 2009/02/12
    ジャーナル フリー
    The Atomic Fuel Corporation has been paying a great effort for the development of uranium mines in this country since its establishment in 1956. The prospecting has so far been centered on the uranium deposits stretching, round Ningyo-toge Mine.
    The underground prospecting investigating on the feasibility of industrialization of the mine has been done with similar method of ordinary metal mines. Moreover, suitable drifting method has been carried out in conjunction with the progress of prospecting on sedimentary uranium deposits.
    Although there were many difficulties for the ore reserve calculations because of the wide varieties of the seam thickness and the grades of ores, a suitable method has been applied to the calculation as a result of research.
    At present, the stoping method is in the testing stage as the type of the deposit is different from those in other parts of this country and in the world. As preliminary testing, two stoping methods, namely the pillar method and the long wall method using the iron props and caps of the ordinary coal mines have been tested and brought about a success. Aiming at the raising of the efficiency, excavation and face conveying method have been put under testing.
    For the safety of the mine, an attention was given to the special nature of the mine as a nuclear source material producting mine and a special policy has been applied in addition to those of the ordinary metal mines.
  • 菅野 昌義
    1960 年 2 巻 12 号 p. 767-778
    発行日: 1960/12/30
    公開日: 2009/02/12
    ジャーナル フリー
    Development of pyrometallurgical processing of irradiated nuclear fuels has been under way for several years. Interest in various processes has grown because they may serve as an aid to reduce fuel processing costs through the possibility of handling short-cooled fuels as well as the elimination of chemical conversions. Information is included in this review on melt refining, liquid-metal and salt processes, fractional crystallization, electrolytic purification and so on. The application of pyrometallurgical techniques to ceramic fuels is mentioned also.
  • 1960 年 2 巻 12 号 p. 779-781
    発行日: 1960/12/30
    公開日: 2009/02/12
    ジャーナル フリー
  • 1960 年 2 巻 12 号 p. 781
    発行日: 1960年
    公開日: 2009/02/12
    ジャーナル フリー
  • 1960 年 2 巻 12 号 p. 782-791
    発行日: 1960/12/30
    公開日: 2009/02/12
    ジャーナル フリー
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