日本原子力学会誌
Online ISSN : 2186-5256
Print ISSN : 0004-7120
ISSN-L : 0004-7120
3 巻, 10 号
選択された号の論文の10件中1~10を表示しています
  • 上野 馨, 張 昭鼎
    1961 年 3 巻 10 号 p. 757-762
    発行日: 1961/10/30
    公開日: 2009/03/26
    ジャーナル フリー
    ジメチル-ベンジル-フェニルアンモニウム塩化物の0.1Mクロロホルム溶液と塩酸の系における,ナトリウムよりネプツニウムに至る約60種の元素の行動を輸入またはJRR-1で照射して作った放射性核種を用いて調べた。水溶液の塩酸の濃度は0.5, 1, 2, 4, 6, 8, 10および12Nの8点をとり,これに対する有機相との間の分配比を求めた。分配比の測定に用いた放射性核種の原子価は明瞭でないものもあるが,最も普通の化学形を選んだ。酸の濃度に対する分配比は各元素により異なるが,周期律表の族についてはかなりの規則性がみられた。 Fe (III)では特に鉄の量の変化による分配比の変化を調べた。これらの結果より数種の元素の相互分離に適した酸の濃度が求められた。
    この系で求められた結果を塩酸-陰イオン交換樹脂系や,チオシアン酸-トリエチル-ベンジルアンモニウム塩化物系と比較しかなりの類似点を見出したが,一般にこの系では分配比が小さいことがわかった。
  • 市坡 純雄
    1961 年 3 巻 10 号 p. 763-766
    発行日: 1961/10/30
    公開日: 2009/03/26
    ジャーナル フリー
    The lattice deffect in graphite was studied by the use of the emanating fission product xenon which was trapped in graphite by the fission recoil.
    Four peaks were found in the heating curve of natural graphite but not in the case of artificial graphite. The activation energies for xenon release were measured at the temperatures where these peaks appear. The observed activation energies at each peak were compared with the calculated values and the classification of lattice deffects was considered.
    The lattice deffects in natural graphite were caused by fission recoil and they were elucidated as the interstitial cluster, single vacancy, combination of single vacancies, and di-vacancy, respectively.
  • 石森 富太郎, 中村 永子, 吾勝 常勲
    1961 年 3 巻 10 号 p. 767-769
    発行日: 1961/10/30
    公開日: 2009/03/26
    ジャーナル フリー
    テクネチウムがジチゾン塩をつくることは従来知られていなかった。
    還元剤の共存下で,テクネチウムは0.1M硝酸よりジチゾン・クロロホルム(四塩化炭素)溶液に抽出される。還元剤ジチゾンがなければほとんど抽出されない。また,有機層のテクネチウムは過酸化水素をふくむ0.1M硝酸または>4M硝酸で逆抽出される。以上の事実を99Tcトレーサを用いて放射化学的に証明し,テクネチウムのジチゾン塩形式を結論した。
    さらに,ジチゾン濃度を変化させた時のテクネチウムの分配比の変化から,この錯塩はテクネチウム1原子あたり,ジチゾン残基2つをふくむものと推論した。
  • 電解・交換反応法+水精溜法+回収電解法
    清水 正巳, 川島 邦夫, 仁藤 三朗, 松本 正三
    1961 年 3 巻 10 号 p. 770-778
    発行日: 1961/10/30
    公開日: 2009/03/26
    ジャーナル フリー
    An analysis to get the most economical combination of three methods of heavy water enrichment, such as elctrolysis-exchange reaction, distillation and recovery electrolysis was made under the condition that the heavy water solution, by-product from a normal water electrolysis plant is available as a raw material.
    As the result, the following combination was obtained as the optimum enrichment cascade in the case we are going to plan.
    4 stages of electrolysis-exchange towers up to 3 wt% of D2O
    Distillation plant from 3 to 28.8 of D2O

    Recovery electrolysis plant from 28.8 to 99.8 of D2O
  • クリープ中におこるcavitationとcracking現象
    長崎 隆吉, 白石 健介
    1961 年 3 巻 10 号 p. 779-786
    発行日: 1961/10/30
    公開日: 2009/03/26
    ジャーナル フリー
    Creep tests have been carried out on Magnox, Mg-1% Al and Mg-1% Zr alloys at several temperatures in the range from 300° to 500°C under several stresses in the range from 0.15 to 0.38kg/mm2. After the creep test specimens were cut out to investigate the phenomenon of cavitation in these alloys during creep test.
    Average creep rates of Magnox alloys under the condition described above are the order of 10-310-1%/hr and Magnox A12 possesses higher creep strength than other Magnox alloys. Creep specimens show ductile fracture at the temperature of 400°C or above and brittle fracture at the temperature of 300°C or below. The surface of the specimen becomes rough by creep deformation.
    Cavities are formed preferentially in grain boundaries normal to the stress axis at early stage of secondary creep mainly caused by grain boundary sliding. In the case of higher stress cavities and cracks are mainly created at triple points of grain boundaries. At constant temperature, for a given amount of strain the number of cavities increases with decreasing strain rate and for a given strain rate it increases with total amount of strain. Cavities are formed easily at the temperature range from 300° to 400°C and they are not formed at the temperature of 500°C and above.
  • 木谷 進, 江連 秀夫
    1961 年 3 巻 10 号 p. 787-791
    発行日: 1961/10/30
    公開日: 2009/03/26
    ジャーナル フリー
    放射線防御の立場から原子炉およびその関連設備において事故あるいは再処理等により,空気中に放出される放射性ヨウ素の除去に相当な注意が払われるべきである。この論文はモレキュラーシーブ5Aによる吸着法によって,ヨウ素蒸気を除去するために行なわれた研究結果である。
    実験結果によれば,高温度ではヨウ素蒸気の吸着過程において水蒸気の影響をうけない利点があるが,吸着量が少ない。それゆえモレキュラーシーブ5Aを放射性ヨウ素蒸気の強力な吸着剤として用いるためには適当な水蒸気吸着剤と併用して低温度で用いるべきである。最適条件では10-6mmHg程度の低濃度まで除去することが可能である。
  • 藤江 秀夫, 遊佐 英夫, 青木 直司
    1961 年 3 巻 10 号 p. 792-799
    発行日: 1961/10/30
    公開日: 2009/03/26
    ジャーナル フリー
    Experiments of steam separation have been made to analyse the phenomena of moisture entrainment into steam from the steam-water mixture in steam generators, such as boiling water reactors (BWR) and conventional shell and tube type steam generators. The height from the boiling surface to the steam outlet, the steam velocity above the boiling surface and the pressure in the steam generator, these three factors are considered as the most important ones with respect to the amount of moisture entrainment. Some clear correlations between the entrainment and these three factors have been found from the test results, in which the pressure was varied from 1 to 70 ata, the steam velocity up to 2.0 m/sec and the height up to 120 cm. The performances of corrugated plate type steam scrubbers have also been tested at atmospheric pressure. The following facts have been confirmed from the test results and the theoretical analysis based on some assumptions.
    (1) The steam quality was almost independent of the height from the boiling surface to the steam outlet when the height is more than 60 cm.
    (2) The steam quality was more deteriorated at the higher pressure.
    However, the quality, at least 99.9%, was obtained at the pressure of 70 ata.
  • 浜口 博, 黒田 六郎, 清水 恒雄, 杉下 竜一郎, 束原 巌, 山本 隆一
    1961 年 3 巻 10 号 p. 800-805
    発行日: 1961/10/30
    公開日: 2009/03/26
    ジャーナル フリー
    The simultaneous determination of microgram to submicrogram amounts of molybdenum, tin, tantalum and tungsten in silicate rocks was arrived at using the Japanese neutron reactor JRR-1. A sample and comparative standard were irradiated simultaneously with a neutron flux of about 3·1011n·cm-2·sec-1 for 3 days (intermittently, 5 hr each day).
    After cooling for a day, the sample was decomposed with sulfuric and hydrofluoric acids in the presence of carriers and lanthanum hold-back carrier. Following the removal of lanthanide activities as fluorides, the fluoride complex of tantalum was extracted by isopropylacetone. Tin and molybdenum was precipitated with hydrogen sulfide from the remaining activities in the aqueous phase, to which boric and tartaric acids were added to mask hydrofluoric acid and tungstate ions, respectively. The α-benzoinoxime precipitation method was then applied for the recovery of bulk of tungsten in the filtrate from the sulfides. Further decontamination chemistry was carried out for each element.
    The amount of the elements was estimated by comparing 99Mo(67 hr), 121Sn(27.5 hr), 182Ta(111d) and 187W(23.9 hr) β-activities isolated from the sample with those from the comparative standard. Sensitivities of the method were 1 ppm for Mo and Sn, 0.1 ppm for Ta and 0.01 ppm for W.
  • 1961 年 3 巻 10 号 p. 806-819
    発行日: 1961/10/30
    公開日: 2009/03/26
    ジャーナル フリー
  • 1961 年 3 巻 10 号 p. 820-822
    発行日: 1961/10/30
    公開日: 2009/03/26
    ジャーナル フリー
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