巻号一覧
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11 巻, 6 号
選択された号の論文の7件中1～7を表示しています
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阪上 正信, 中西 孝1969 年 11 巻 6 号 p. 332-339
発行日: 1969/06/30
公開日: 2010/04/19
ジャーナル フリーMeasurements of thermal and fast neutron fluxes in a mixed radiation field have been carried out by etching technique applied to fission tracks on a mica detector. As fissionable material, use was made of electrochemical deposits-on Au-coated Cu-plate or stainless steel plate-of 232Th, 231Pa, natural U, depleted U, 232U, 237Np, 238Pu and 239Pu. The atomic density of the fissionable material on the plate was measured by α-spedrometry. These plates were placed in contact with muscovite mica, and exposed to neutron flux in a TRIGA Mark-II nuclear reactor, both with and without thermal neutron absorber of Cd. After the irradiation, the mica was etched by hydrofluoric acid solution, and the track density counted on a microphotograph. The values of the thermal and fast neutron fluxes were obtained from the mean cross-section of the fission reactions undergone by the different nuclides present. The resulting flux values showed reasonably good agreement with the values obtained by other methods. A discussion is given on the nuclear data obtained for several nuclides. A proposal is presented also on a simple and practical method for determining high track density by photometer with dark-field illumination.抄録全体を表示PDF形式でダウンロード (4947K) -
反応性水溶液のスプレイによるヨウ素水洗効果西沢 千父, 大島 茂男, 前川 立夫1969 年 11 巻 6 号 p. 340-346
発行日: 1969/06/30
公開日: 2010/04/19
ジャーナル フリーWashout removal of iodine from atmosphere by reactive spray was studied with the use of small-scale steel vessels simulating containment. The washout experiments in the range of 25° to 80°C were performed under normal steady state spray, while runs at 100° to 150°C utilized spray accompanied by cooling, the steam pressure being that of equilibrium for the temperature of the experiment. The iodine removal rate was evaluated by varying the gas phase concentration which was determined by thiosulfate titration.
It was found as a result that the washout rates of iodine by a spray of 0.1 to 1M NaOH solution were thirty to seventy times as fast as by plain city water, and that the rates were independent of temperature. A similar degree of enhancement was observed with sodium thiosulfate solution. An even greater effect was obtained with sodium sulfite solution. The rate of iodine washout was found to be expressible by first order equation, which suggested gas film controlled absorption as the mechanism of iodine absorption in the liquid drops.抄録全体を表示PDF形式でダウンロード (377K) -
古川 友三1969 年 11 巻 6 号 p. 347-352
発行日: 1969/06/30
公開日: 2010/04/19
ジャーナル フリーAs measures to determine the performance of log N period meters, use can be made of (a) fluctuations due to statistical data from the detection process, (b) power overshoot due to scram delay, and (c) transient overshoot during a given period. While (a) is related to the time constants by a simple analytical expression, evaluation of (b) and (c) requires numerical calculation. This paper presents convenient formats for data sheets to be used in evaluating the performances (b) and (c) accompanying exponentially increasing power. The parameters are chosen as follows: (a) Inverse period of exponentially increasing power normalized with reference to scram level, (b) time constant of the period meter similarly normalized, and (c) initiating time constant of log N amplifier normalized with reference to period meter time constant. The following behavior has been noted: (a) When the margin of power overshoot is the preponderant factor, evaluation of the transient initiated at a high power is enough, (b) the transient overshoot represented in terms of inverse period has a maximum at a certain period meter time constant. Using these data sheets, the constants, commonly used in reactor instrumentation in Japan have been rescrutized, and proposals presented on the necessity and the possibility of revising them.抄録全体を表示PDF形式でダウンロード (386K) -
野村 末雄1969 年 11 巻 6 号 p. 353-361
発行日: 1969/06/30
公開日: 2010/04/19
ジャーナル フリーCorrosion of reactor materials under irradiation is reviewed and discussed from the standpoint of the effect of: (1) radiation damage in metals, (2) radiation damage in oxide film, and (3) radiation effect on corrosion environment.
Radiation damage on metal surface stimulates the dissolution of the metal into aqueous solution and reduces its electrode potential. Studies at Harwell and ORNL have proved that high temperature aqueous corrosion of Zr and Zry-2 is accelerated by damage in the metal substrata rather than on the surface oxide film.
The effect on corrosion brought by damage in the oxide film is explained in terms of increases in density, in electronic conductivity, in diffusivity and in surface chemical reactivity.
Radiolysis of the aqueous environment also influences the corrosion of metal through changes in the electrochemical properties of solution and of metal electrode.抄録全体を表示PDF形式でダウンロード (681K) -
ドンレーFBRの運転経験中川 弘, 二見 常夫1969 年 11 巻 6 号 p. 362-368
発行日: 1969/06/30
公開日: 2010/04/19
ジャーナル フリーAs a sequel to the precedent report (Vol. 11, Nos. 4 and 5, this Journal), the present article reviews and evaluates the operating experience of the Dounreay FBR.抄録全体を表示PDF形式でダウンロード (517K) -
三木 良平, 鈴木 庸一1969 年 11 巻 6 号 p. 369-375
発行日: 1969/06/30
公開日: 2010/04/19
ジャーナル フリーThe objective of the Japanese prototype fast breeder reactor project is to con struct a mixed oxide fueled prototype fast breeder reactor of 200 to 300MWe capacity through the application of domestic technology with the contribution of associated work in research and development.
The initial design work is expected to start in the hands of the Power Reactor and Nuclear Fuel Development Corporation (PNC) in the summer of 1969, but to prepare for this, PNC commissioned representative Japanese manufactures to submit preliminary designs based on summary specifications. The purpose of this preliminary design study was to let the manufacturers design a prototype fast breeder reactor plant untrammeled by restrictive conditions, to permit their embodying original ideas and concepts, which might eventually be adopted and incorporated in PNC's prototype reactor project.
The design study was made over a period of five months between September 1968 and January 1969, the companies commissioned being Fuji Electric Co., Ltd., Hitachi Ltd., Mitsubishi Atomic Power Industries, Inc., Sumitomo Atomic Energy Industries, Ltd. and Tokyo Shibaura Electric Co., Ltd.
A brief summary of the result of this preliminary design study is presented, with schematic illustrations of the reactor structure, fuel handling system and steam generator constituting the different reactor plans submitted.抄録全体を表示PDF形式でダウンロード (10909K) -
浜口 俊一1969 年 11 巻 6 号 p. 376-385
発行日: 1969/06/30
公開日: 2010/04/19
ジャーナル フリーPDF形式でダウンロード (7610K)
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