日本原子力学会誌
Online ISSN : 2186-5256
Print ISSN : 0004-7120
ISSN-L : 0004-7120
18 巻, 7 号
選択された号の論文の10件中1~10を表示しています
  • 石川 義和
    1976 年 18 巻 7 号 p. 401-407
    発行日: 1976/07/30
    公開日: 2009/03/31
    ジャーナル フリー
    まず加速器を用いて,中性子をパルス的に発生させる「パルス中性子源」の中性子散乱研究への有用性を一般的に述ぺる。次に,東北大核理研の電子ライナックを用いて行われている中性子散乱実験の概要を記述した後に,高エネルギー研のプロトンブースターによる中性子源計画を紹介する。
  • 尾熊 律雄, 松原 邦彦, 北村 正晴
    1976 年 18 巻 7 号 p. 408-414
    発行日: 1976/07/30
    公開日: 2009/03/31
    ジャーナル フリー
    実験データをペースにして動特性モデルを作っていく方法,いわゆるシステムの同定手法について,最近の新しい手法を紹介し,原子炉診断技術および炉雑音解析の分野にどう応用していくことができるか,その一端を述べる。また,同定手法の具体的応用例として, JPDR同定実験,解析結果について解説し,得られた経験等も含めて応用上の問題点を指摘する。
  • 塩川 孝信, 鍛冶 東海
    1976 年 18 巻 7 号 p. 415-422
    発行日: 1976/07/30
    公開日: 2009/03/31
    ジャーナル フリー
    荷電粒子により原子が励起されて,特性X線を発生する反応断面積が大きく,かつこのX線の測定にあたっては, Si(Li)もしくはX線用Ge(Li)検出器を用いると,非破壊で同時に多元素が試料として微少量でppmのオーダの分析が容易にできる。
    本稿では,その原理,検出感度,実験法,問題点等を解説し,あわせて実験例を紹介する。
  • 安久津 英男, 武藤 正
    1976 年 18 巻 7 号 p. 423-432
    発行日: 1976/07/30
    公開日: 2009/03/31
    ジャーナル フリー
    The result and experience on Pu fuels and their handling in Power Reactor and Nuclear Fuel Development Corp. are compiled in memory of the 10th anniversary of establishment of the first Pu fuel laboratory on Nov. 26, 1960. The second facility was built at the end of 1971 as a Pu fuel fabrication facility. The amount of Pu fuels fabricated in both facilities reached 15, 000 fuel rods with 13t of mixed oxide pellets mostly for JOYO and DCA, and is further increasing for FUGEN. Quality assurance system has been arranged in accordance with increase of the fuel produced, and a fully documented system was completed for the FUGEN Pu fuel.
    Research and development work for Pu fuels has been focussed on physical properties of mixed oxide, and in and out of pile evaluation of the fuel performance together with some activities related to Pu fuel design, and these results have been compiled in computer codes including fuel performance codes, PIPER and ACTIVE-II. Irradiation testings of the mixed oxide fuels totaling 418 rods were carried out successfully in JRR-2, JMTR, HBWR, SAXTON, GETR, Rapsodie and Dounreay. Besides, 3, 624 fuel rods were fabricated and used for critical experiments in DCA, TCA, etc.
    Concerning the safety control against Pu handling were described control systems for confinement, criticality, accountancy, radiation exposure, and safeguarding, stressed on socalled “zero contamination control”.
  • 原研における測定法およびIAEA主催の国際比較実験
    備後 一義
    1976 年 18 巻 7 号 p. 433-437
    発行日: 1976/07/30
    公開日: 2009/03/31
    ジャーナル フリー
    Historical reviews on Nuclear Accident Dosimetry (NAD), at first, are described briefly. The NAD system in Japan Atomic Energy Research Institute is also described. The system consists of six fission track detectors and a disk of sulfur for neutrons and the JAERI Model IV film badge, in which TLDs are added, for γ-rays. The lower limit of dose estimation for neutrons is about 1 rad.
    The IV IAEA Intercomparison Experiment on NAD was held at Harwell, UK, 718 April 1975. Seventeen institutes from 30 countries were participated. A summary of the experiment is shown.
  • 武田 宏, 山本 寛
    1976 年 18 巻 7 号 p. 440-442
    発行日: 1976/07/30
    公開日: 2009/03/31
    ジャーナル フリー
  • 「欧文誌」投稿者のために
    吉田 正男
    1976 年 18 巻 7 号 p. 443-444
    発行日: 1976/07/30
    公開日: 2009/03/31
    ジャーナル フリー
  • 井上 頼輝, 森澤 眞輔, 宮武 法善
    1976 年 18 巻 7 号 p. 445-451
    発行日: 1976/07/30
    公開日: 2009/03/31
    ジャーナル フリー
    Some kind of radionuclides, those are stable in an non-ionic form in water, are evaluated experimentally to migrate through saturated zone (groundwater bearing zone) as fast as groundwater.
    In this report, non-ionic form of 90Y in water and the migration characteristics of 90Y through sand column were examined experimentally and some valuable results were obtained: (1) Yttrium-90 are stable in a cationic ion in a low pH range of water and in a nonionic form in a high pH range. This non-ionic 90Y has no electric charge on it. (2) Some part of non-ionic 90Y are sorbed by a sample sand but the other part are not sorbed. The amount of former 90Y decreases along with a pH increase, and (3) In a pH range which are usally observed in a natural saturated zone, large fraction of 90Y might be transported as fast as groundwater. New method or theory should be examined for evaluating 90Y migration, based on a specific performance of non-ionic 90Y in the ground.
  • 重富 康正, 小嶋 健博, 品川 睦明
    1976 年 18 巻 7 号 p. 452-457
    発行日: 1976/07/30
    公開日: 2009/03/31
    ジャーナル フリー
    A fundamental experiment to concentrate U in sea water by a new technique “interfacial electrolysis” was carried out. The artificial sea water were prepared from sodium chloride, magnesium chloride and U (VI).
    Two liters of the solution was brought in contact with 500 ml of isobutylalcohol in a 3 l beaker and the electrolysis was carried out. The cathode disk, stainless steel plate with a diameter of 14 cm, was set in the organic phase and the anode, platinium wire was dipped in the aqueous phase. Uranium (VI) was quantitatively coprecipitated with magnesium hydroxide produced at the interface by the electrolysis.
    The method was applied to the concentration of U from sea water and the result was compared with that of the usual coprecipitation of magnesium hydroxide precipitated by sodium hydroxide. Magnesium hydroxide which was obtained by the electrolysis using the solution, involved 15.5 μg of U and 2, 430 mg of Mg, contained 15 μg of U and 15 mg of Mg, and that was very easy for filtration. On the other hand, by sodium hydroxide precipitation method, 200 mg of Mg had to be precipitated for the sake of 15 μg U coprecipitation. It took about 4.0 hr for the above mentioned electrolytic precipitation from 2 l of sea water. The collection of U was about 90% in regard to the natural content in sea water.
  • 1976 年 18 巻 7 号 p. 458
    発行日: 1976/07/30
    公開日: 2009/03/31
    ジャーナル フリー
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