巻号一覧
後続誌
5 巻, 11 号
選択された号の論文の9件中1～9を表示しています
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水田 三千雄, 橋本 清, 加藤 道男1963 年 5 巻 11 号 p. 903-908
発行日: 1963/11/30
公開日: 2009/03/26
ジャーナル フリーTo obtain fundamental informations on the fabrication technology of a control rod absorber of Ag-15_??_In-5_??_Cd alloy, which was developed considering the Hume-Rothery electron concentration rule, some experiments were performed. By the hardness tests on alloys obtained in several steps of cold rolling and subsequent annealing, the alloy was confirmed to have good workability. The cast alloy was able to be extruded at 700°C in round rods. The value of extrusion coefficient “K” was determined to be about 15kg/mm2 at 700°C. The tensile properties and microstructures of extruded rods were studied.抄録全体を表示PDF形式でダウンロード (1772K) -
宇津呂 雄彦, 桜井 良文1963 年 5 巻 11 号 p. 908-916
発行日: 1963/11/30
公開日: 2009/03/26
ジャーナル フリーIn this paper, a zero power reactor simulator and thermodynamic-hydrodynamic coolant loops were used to investigate BWR dynamics. The instability which appeared in thermodynamic and hydrodynamic loops in natural circulation condition is the most noticeable phenomenon. To investigate the instability, we operated the boiling loops only as the first step.
Combining the zero power reactor simulator and thermodynamic-hydrodynamic loops in a closed form by use of an electric capacitor type of void fraction detecting device, we obtained satisfactory results in BWR simulation. Effects of void coefficient of reactivity on the whole BWR dynamics were investigated, also the influences of the coolant circulation condition were investigated.
From these experimental results, it was concluded that the properties of power-void feedback transfer function have the predominant effects on the overall reactor dynamics. So, we investigated further the power-void transfer function and compared it with the theoretical transfer function. We proceeded further the theoretical approaches to understand the interesting tendencies which appeared in experimental power-void transfer function.抄録全体を表示PDF形式でダウンロード (465K) -
馬場 宏1963 年 5 巻 11 号 p. 917-925
発行日: 1963/11/30
公開日: 2009/03/26
ジャーナル フリーChemical distribution of 32P formed by neutron irradiation in a nuclear reactor was studied as a function of degree of hydration, number of acid hydrogen and ionic radii of cations in various orthophosphates, sodium pyrophosphate. sodium phosphite and sodium hypophosphite. The separation of chemical species containing 32P was done by paper partition chromatography.
It was noticed that the chemical distribution of 32P was effected by hydrated water in target materials so as to increase the retention as parent form and to change the stability of reduced species. As the discrepancies between retention values in a series of sodium orthophosphates were correlated to the number of acid hydrogen in samples, it was suggested that these effects were probably caused by the reducing action of acid hydrogen to the distributed species. On the effect of cations to the chemical distribution of 32P in irradiated various tertiaryphosphates, it was found that the percentage in each fraction was dependent upon ionic radii of cations. Three groups were shown in this case according to the valence states of cations. Each group was represented by one curve clearly different from others based on ionic radii of cations. The change of retention as parent form was proportional to the ionic radii of cations.抄録全体を表示PDF形式でダウンロード (484K) -
真室 哲雄, 石山 稔雄, 松村 隆1963 年 5 巻 11 号 p. 925-932
発行日: 1963/11/30
公開日: 2009/03/26
ジャーナル フリーThe volume reduction of radioactive sludges is one of the most important problems involved in the large scale treatment of weakly contaminated liquid wastes through flocculation. A small plant has been constructed at the Radiation Center of Osaka Pref. in March of 1962, which is the first attempt in Japan that adopts the freezing treatment for concentrating radioactive sludges. The volume reduction characteristic of this plant has been investigated. This plant can handle 125l of sludge per day and can reduce the final volume of the concentrated sludge to about 1/5, 000, 1/2, 000 and 1/4, 000 of the volume of the original waste water to be decontaminated, for bentonite-Konan Floc sludge, calcium phosphate sludge and ferric hydroxide sludge, respectively, in the case that the separation by settling is applied as the treatment after thawing. Appreciably higher volume reduction ratio can be obtained when the vacuum filtration is applied after thawing. In the beaker-experiments which were carried out before the present investigation, it was found that the addition of some polymer as agent is effective in improving the volume reduction or in shortening the settling time after thawing. This finding has been applied for the large scale treatment by this plant and good results as expected have been obtained.抄録全体を表示PDF形式でダウンロード (3141K) -
水科 篤郎, 高松 武一郎, 三石 信雄, 福本 勤, 山田 卓1963 年 5 巻 11 号 p. 933-938
発行日: 1963/11/30
公開日: 2009/03/26
ジャーナル フリーWith the progress of atomic energy industry, the treatment of radioactive waste solutions has become an important problem. As one of the safest and surest methods of the treatment of the solutions, concentration by evaporation is recommended. However, in the case of using a current standard type evaporator, those organic materials in the solutions which are sensitive to heat often decompose on account of their long stay in the evaporators, and excessive foaming and entrainment often produce radioactive condensates, making the process inefficient. This is the reason why the use of a falling film evaporator has been proposed, and the authors manufactured a test apparatus and studied its decontamination capacity, using water and CMC aqueous solutions as Newtonian and non-Newtonian fluids respectively and LiCl as a tracer.
The results are as follows: (1) When the liquid flow rates are 200300l/hr, and vapor mass velocities 1001, 000 kg/m2hr, the decontamination factors are about 105 for the Newtonian fluid, which coincides well with the results previously obtained by one of the authors who used a standard type evaporator, and about 104 for the non-Newtonian fluids. (2) The mean retention time for the Newtonian fluid is about 0.26 sec, and that for the non-Newtonian fluid about 3.2sec, when the liquid flow rate is about 200l/hr.抄録全体を表示PDF形式でダウンロード (358K) -
生豚皮の90Sr-90Yおよび32Pによる汚染和達 嘉樹, 田代 晋吾, 田島 雄三, 檜山 哲男1963 年 5 巻 11 号 p. 938-943
発行日: 1963/11/30
公開日: 2009/03/26
ジャーナル フリーIn order to study the mechanism of skin contamination, the experiment was carried out by a fresh pig skin. The pig skin was contaminated with carrier free 90Sr-90Y or 32P and after a certain time elapsed, it was sliced off about 0.5mm in thickness. The adhered contamination of outer skin (abbr.; the adhered contamination) or the permeated contamination of inner skin (abbr.; the permeated contamination) in each sliced sample was measured by low back ground G-M counter. The result obtained showed that in regard to 90Sr-90Y and 32P, the adhered contamination changed extraordinarily within 60 min after contamination and then it incresed gradually with an increase of contaminating time and that particularly in the case of 90Sr-90Y, pH of contaminating solution affected much the adhered contamination. Furthermore, 90Y showed a selective adhesion at the broad pH region, that is, from a weak acidity to an alkalinity. On the other hand, the result obtained showed that in regard to 90Sr-90Y and 32P, the permeated contamination increased with an increase of contaminating time and that 32P permeated quickly more into the inside of skin than that of 90Sr-90Y. 90Y contributed greatly to the permeated contamination as well as to the adhered contamination, if pH of 90Sr-90Y solution is over 4.5.抄録全体を表示PDF形式でダウンロード (307K) -
高橋 博1963 年 5 巻 11 号 p. 944-952
発行日: 1963/11/30
公開日: 2009/03/26
ジャーナル フリーEigenvalue problem in time and space dependent thermalization transport equation are summarized. They are important in analysis of time decay constant λ and diiffusion length 1/κ measurements. A study of the Wigner-Wilkins type differential equation for the proton gas moderator indicates the existence of an infinite number of discrete time dependent eigenvalue λκ in the range 0≤λκ<(υΣ)min and of a continuous eigenvalue λ in the range (υΣ)min<λ which has a singular eigenfunction. A method of singular integral equation developed by Muskhelishvili is used in order to prove the existence of the singular eigenfunction in the case of more general scattering kernel. They are compared with a expansion method of a flux in terms of polynomials of energy or of velocity. A boundness of time eigenvalues of infinite and finite medium are illustrated for the both cases of mono energetic neutron and thermalizing neutron. The relevance of Boltzmann transport equation is studied for the very slow neutron. Finally the discussion of the spacial eigenvalue problem is added.抄録全体を表示PDF形式でダウンロード (614K) -
放射性同位元素を用いた直接発電J. G. MORSE1963 年 5 巻 11 号 p. 953-956
発行日: 1963/11/30
公開日: 2009/03/26
ジャーナル フリーPDF形式でダウンロード (3007K) -
1963 年 5 巻 11 号 p. 957-959
発行日: 1963/11/30
公開日: 2009/03/26
ジャーナル フリーPDF形式でダウンロード (203K)
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