巻号一覧
後続誌
5 巻, 8 号
選択された号の論文の12件中1～12を表示しています
- |<
- <
- 1
- >
- >|
-
石森 富太郎, 木村 幹, 中村 永子, 吾勝 常勲, 小船 敏子1963 年 5 巻 8 号 p. 633-639
発行日: 1963/08/30
公開日: 2009/03/26
ジャーナル フリーA radiochemical study on the solvent extraction behavior of about sixty chemical elements performed in 10% TBEDP- and 10% TBMDP-nitric acid systems, respectively. The acidity of the aqueous phase was changed from 1 to 15N.
The acid dependence curves obtained for each element were very similar between the two systems studied. Considerable regularities were found with respect to the extraction behavior of the corresponding congeners. It was also found that the present results for both systems are fairly similar to those of 100% TBP-HNO3 system.抄録全体を表示PDF形式でダウンロード (276K) -
α-オキシイソ酪酸による陽イオン交換藤野 威男1963 年 5 巻 8 号 p. 640-643
発行日: 1963/08/30
公開日: 2009/03/26
ジャーナル フリー242Cm was separated from JRR-1 irradiated 241Am. The separation was carried out at room temperature by the elution with 0.5M ammonium α-hydroxy isobutyrate of pH 3.68 from the column of 8% cross linked Diaion SK#1. The flow rate of 1 drop/5 min was found to give a good separation of 242Cm from 241Am. The separation factor was calculated to be 1.49. Radiochemical purity of curium fraction was checked by means of decay curve and α pulse height analyses.抄録全体を表示PDF形式でダウンロード (198K) -
沈殿法および陰イオン交換法の組合せによる35Sの分離四方 英治1963 年 5 巻 8 号 p. 644-651
発行日: 1963/08/30
公開日: 2009/03/26
ジャーナル フリーTen grams of the neutron-irradiated potassium chloride were dissolved in 20 ml of boiling water, which contained 10 mg of phosphate. Sixty milliliters of ethanol were added to the solution. After being cooled to room temperature potassium chloride precipitate was filtered off. The filtrate was diluted by the addition of 300 ml of water and passed through an anion exchange resin column in chloride form. The column was washed with water. 32P was eluted with 0.05N hydrochloric acid and then 35S with 2N hydrochloric acid. Various conditions of the separation and the quality of 35S prepared by this method were investigated. By the pre-treatment with ethanol prior to the anion exchange separation, the Kd value of 35S(35S42-) against the anion exchange resin was increased without increasing the volume of the solution and the separation was made easily. The specific activity of 35S prepared by this method was about ten times as high as that prepared by the cation exchange method. The percentage of 35S recovered was about 80%. The separation factor against 32P formed simultaneously by the neutron irradiation was 1.3×104 at maximum.抄録全体を表示PDF形式でダウンロード (419K) -
亀本 雄一郎, 萩谷 公子, 山岸 滋1963 年 5 巻 8 号 p. 652-656
発行日: 1963/08/30
公開日: 2009/03/26
ジャーナル フリーFocussing chromatography was applied to the mutual separation of rare earth elements and the effect of several conditions upon the separation of rare earth elements was studied. The most satisfactory result was obtained in the conditions as follows: 0.1 M citric acid was used as the complexing agent and 0.01 N hydrochloric acid as the decomplexing agent, pH gradient of both solutions between anode and cathode was pH 2.8 (HCl)-4.4 (citric acid), the rare earth solutions contained no nitric acid, the applied voltage was 1, 000V/30 cm, the treatment time was 20 min, and the filter paper was Toyo Roshi No. 50.
After treatment of separation, the autoradiographic technique was employed to decide the position of each separated line.抄録全体を表示PDF形式でダウンロード (266K) -
松村 隆, 石山 稔雄, 真室 哲雄1963 年 5 巻 8 号 p. 656-662
発行日: 1963/08/30
公開日: 2009/03/26
ジャーナル フリーRecently flocculators of slurry circulation type have been adopted at various institutes in Japan for the treatment of weakly contaminated radioactive waste water. The mechanism of decontamination in the flocculator is, however, still not enough realized. There are some problems which should be solved in order to make best use of the flocculator. For this purpose, the experiments involving the test flocculations in beakers and in a small flocculator have been carried out in the case of ferric hydroxide flocculation. Among the results obtained, the following facts were considered to be noticeable.
(1) The pH value of the reacting medium has a serious effect on the removal.
(2) As for radioactive ions, the main decontamination process is completed in the stage that the ferric hydroxide particles are formed in the reacting medium. The continuation of strring after this stage gives rise to no further improvement in the removal.
(3) The removal of Sr is effectively raised by the addition of equivalent or more amount of carbonate ion when the waste water to be decontaminated contains alkali earth metal ions.
(4) Noticeable difference in the removal is not found between the flocculations in a beaker and in a flocculator under the same flocculation conditions.
(5) The main role of slurry circulation type flocculator in the decontamination of radioactive waste water is to clarify the effuluent by dynamical separation of solid from liquid.抄録全体を表示PDF形式でダウンロード (373K) -
浜口 博, 黒田 六郎, 細原 匡一, 清水 恒雄1963 年 5 巻 8 号 p. 662-665
発行日: 1963/08/30
公開日: 2009/03/26
ジャーナル フリーA thermal neutron activation method was worked out for the determination of traces of tantalum in sea water. Before irradiation tantalum was collected into iron hydroxide from 510 l of sea water sample with a satisfactory recovery. Air dried hydroxide was then irradiated along with a reference standard for a period of up to twelve days at the neutron fluxes of 3·1011n·cm-2·sec-1. Solvent extraction separation using hydrofluoric acid-sulfuric acid-isopropylacetone system gave 182Ta (111 d) in a radiochemically pure form. Activity measurements were taken on a β-proportional counter. As little as 0.1 μg of tantalum in a 5 l of water sample can be determined this way.
A detailed description was given for the solvent extraction separation of tantalum. Average tantalum content of sea water was estimated to be 0.00≤0.02 μg/l.抄録全体を表示PDF形式でダウンロード (231K) -
添野 浩1963 年 5 巻 8 号 p. 665-671
発行日: 1963/08/30
公開日: 2009/03/26
ジャーナル フリーA series of uranium alloys varying in silicon content 0.51.0 _??_ were studied. The tendency of the β or γ phase uranium to retain upon quenching was examined as a function of silicon content. The β phase can be retained at room temperature, while the retention of the γ phase could not be observed at all. TTT diagrams and microstructures after isothermal transformation were studied, and the existence of two modes in the β-to-α transformation is clarified. The Ms temperature of the martensitic β-to-α transformation, which increases with decreasing silicon content, is determined and it is clarified that the suitable grainrefinement is attained by the isothermal transformation in the temperature region slightly higher than Ms temperature.抄録全体を表示PDF形式でダウンロード (1250K) -
矢島 聖使, 亀本 雄一郎, 高橋 良寿1963 年 5 巻 8 号 p. 672-676
発行日: 1963/08/30
公開日: 2009/03/26
ジャーナル フリーIn a basic study using a molten bismuth as a coolant of reactor, the authors made an attempt to manufacture an out-pile loop with graphite, and succeeded in making the loop of no-leakage of bismuth.
In this report, the outline of the structure of this loop was shown. The loop was charged with bismuth by pressurizing the sumptank with nitrogen gas. In operation, the bismuth was pumped by means of a mechanical pump to III, II and I vessels and a flow meter. Temperature of bismuth metal was controled at 550°C (usual) and 700°C (maximum), and was read with chromel-alumel and platinum-platinum, rhodium thermocouples set in 28 points of this loop. Individual piping runs and vessels were wrapped with hot plates of nichrome heater. The total power supplied to groupes of these heaters were maximum 20.12kW.
The pipe consisted of two parts. An inner tube (bismuth piping) was surrounded by hot plate of nichrome heater and an outer tube was surrounded by thermal insulator. In order to protect the inner tube from being oxidized by air, graphite powder was packed between these tubes and nitrogen gas was let flow through this powder.抄録全体を表示PDF形式でダウンロード (1772K) -
吉岡 一彦1963 年 5 巻 8 号 p. 677-683
発行日: 1963/08/30
公開日: 2009/03/26
ジャーナル フリーThe properties of uranium monosulfide are reviewed from a viewpoint of nuclear fuel material. The preparation methods are also described.
As a result of recent researches mainly at ANL, the sulfide is known to be a promising nuclear fuel material because of its high melting point, uranium density comparable to that of UO2, semi-metallic properties, chemical stability and compatibility with some cladding metals.抄録全体を表示PDF形式でダウンロード (1639K) -
1963 年 5 巻 8 号 p. 684-686
発行日: 1963/08/30
公開日: 2009/03/26
ジャーナル フリーPDF形式でダウンロード (915K) -
M. G. TROCHERIS1963 年 5 巻 8 号 p. 687-692
発行日: 1963/08/30
公開日: 2009/03/26
ジャーナル フリーPDF形式でダウンロード (466K) -
J. H. KITTEL1963 年 5 巻 8 号 p. 693-698
発行日: 1963/08/30
公開日: 2009/03/26
ジャーナル フリーPDF形式でダウンロード (4546K)
- |<
- <
- 1
- >
- >|