巻号一覧
後続誌
5 巻, 4 号
選択された号の論文の12件中1～12を表示しています
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35Clの(n, p)および(n, α)反応の研究四方 英治1963 年 5 巻 4 号 p. 269-272
発行日: 1963/04/30
公開日: 2009/03/26
ジャーナル フリー(n, p) and (n, α) reactions on 35Cl were investigated from the viewpoint of 35S production. Potassium chloride was irradiated in various experimental holes of JRR-1 reactor. The activated 35S and 32P were separated and measured. Cross-sections of both reactions for thermal and fission neutron flux were measured. Energy dependencies of the reactions for reactor neutrons and the methods of reducing the amount of 32P formed during irradiation were investigated.抄録全体を表示PDF形式でダウンロード (216K) -
機械的分離方法による二酸化ウランの回収岩本 多実, 下川 純一1963 年 5 巻 4 号 p. 272-279
発行日: 1963/04/30
公開日: 2009/03/26
ジャーナル フリーAn approach to recover UO2 mechanically from the UO2-graphite fuel specimen was investigated. After disintegrating an unirradiated specimen by a pulverizer, ball mill, or micron mill, the obtained powder was separated into the UO2 and graphite phases by a heavy-media-separation method in which a zinc-bromide solution was used as the heavy medium.
The disintegration of the specimen into fine powder was essential for the mechanical separation of UO2.
Additional treatments such as preoxidation of the sample, addition of dispersion agent to the zinc-bromide solution, and irradiation of the solution with the ultrasonic waves, were not effective in improving the UO2 recovery.
However, it seemed that the grinding method coupled with continuous removal of the ground particles with fluid flowing would be effective in obtaining a high UO2 recovery.抄録全体を表示PDF形式でダウンロード (1110K) -
添野 浩1963 年 5 巻 4 号 p. 280-286
発行日: 1963/04/30
公開日: 2009/03/26
ジャーナル フリーThe kinetics of isothermal transformation were studied with uranium alloys varying in iron content 0.51.0 _??_. Two modes of β-to-α transformation, nucleation-and-growth and martensitic transformations, are observed and Ms temperature is determined as a function of iron content. The Ms temperature increases with decreasing iron content, so the martensitic transformation, which produces coarse α-uranium grains, prevails in such alloys of lower content of iron. Nucleation and growth mode is found to be applicable to grain-refinement. And suitable grain-refinement is generally attained by isothermal transformation in the temperature region from 450°C to Ms temperature.抄録全体を表示PDF形式でダウンロード (1161K) -
小沢 保知, 成田 正邦1963 年 5 巻 4 号 p. 286-292
発行日: 1963/04/30
公開日: 2009/03/26
ジャーナル フリーMaximum efficiency condition of MHD power generation have been derived as follows:
(1) Spacialy homogeneous distribution both of induced electro-motive-force and of the ratio of the applied magnetic induction to the density of a working fluid are required for irrespective of compressible or incompressible plasmas.
(2) In case of incompressible plasmas, a homogeneous distribution of the magnetic induction is requested.
(3) The magnitude of the required external loading at optimum and maximum efficiency power conversion is determined and it is proved that the optimum value of loading exists in a light load region.抄録全体を表示PDF形式でダウンロード (370K) -
同位元素のイオン交換分離係数の理論的考察垣花 秀武, 栗栖 紀美子1963 年 5 巻 4 号 p. 292-299
発行日: 1963/04/30
公開日: 2009/03/26
ジャーナル フリーIon exchange separation factors for the quaternary valence isotopes forming stepwise complexes in external solutions have been theoretically evaluated. Two forms of the limits for the separation factors were found both for the anion exchanger and the cation exchanger systems.
For the anion exchanger,
(1) lim=Δlim (ln SAB-lnABK5)=-(5IIm+1Kn-1)
(2) limΔ=-ε/6
limΔ=-(ε-5IIm+1Kn+1)/5
limΔ=-{ε-(5IIm+1Kn-1)-(5IIq+1Kn-1)}/4
For the cation exchanger,
(1) limΔ=-(mII1K-1)
(2) limΔ-ε/6
limΔ=-(ε-mII1Kn+1)/5
limΔ=-{ε-(mII1K-1)-(qII1K-1)}/4
On the anion exchanger system, in case only AX5 being adsorbed on and the very large excess of A existing in the external solution, the effect by five times as large as the ratio of the stability constants of one step complex formation is expected on the separation factor.
On the cation exchanger, the highest effect is expected when only A is adsorbed on and the very large excess of AX6 exists in the external solution. The value for the effect is approximately six times as large as the ratio of the stability constants of one step complex formation.抄録全体を表示PDF形式でダウンロード (370K) -
金子 英二1963 年 5 巻 4 号 p. 299-305
発行日: 1963/04/30
公開日: 2009/03/26
ジャーナル フリーA new transistorized logaritnmic counting rate meter has been developed. It was designed for using in the start up region of nuclear reactor.
The experimental data of this device are given as follows:
(1) Counting region: 0.3 cps30 kcps
(2) Accuracy: ±0.1 decades
(3) Pules resolution: Better than 1μsec
(4) Discri. level: -0.1 V pp-10 V pp
(5) Stability: Better than ±0.05 decades for ±15% change of line voltage and better than ±0.1 decades 0°40°C change of room temperature
(6) Drift: ±0.1 decades/8hr.抄録全体を表示PDF形式でダウンロード (1103K) -
Zr-Cu-Mo合金の基礎的諸性質青木 重夫, 太郎良 績, 橋口 隆吉, 三島 良績1963 年 5 巻 4 号 p. 305-310
発行日: 1963/04/30
公開日: 2009/03/26
ジャーナル フリーThe fundamental properties, such as the physical and mechanical properties, the heat-treatment characteristics and corrosion resistance in high temperature and pressurized CO2 gas, of various Zr-Cu-Mo alloys which are used for the construction material of the fuel element for the gas cooled power reactor, have been investigated. The contents of Cu and Mo as the alloying elements are in the range of 0.51.5%.
Results obtained are summarized as follows:
(1) The transformation temperature from γ to β is about 750°C.
(2) Alloys have good workability and the mechanical properties are nearly same as Zircaloy-2.
(3) Improvements of the mechanical properties are expected by heat-treatment.
(4) These alloys of Zr-0.5%Cu-1.0%Mo, Zr-0.5%Mo and Zr-1.5%Cu-1.5%Mo have good corrosion resistance in high temperature and pressurized CO2 gas.抄録全体を表示PDF形式でダウンロード (319K) -
コールダーホール型燃料の破損に関する研究, (1)武谷 清昭, 井川 勝市1963 年 5 巻 4 号 p. 310-315
発行日: 1963/04/30
公開日: 2009/03/26
ジャーナル フリーAs the first step of a series of experiments designed for the hazards evaluation of the uranium fuel for the Calder-Hall type reactor of Japan Atomic Power Co., behavior of oxidation by air at 550°C has been investigated. The specimen used is a dummy fuel element, Magnox clad uranium rod, with a pinhole on the cladding. The pinhole diameter ranges 0.31.2 mm, and the thickness of the cladding is 1.6 mm.
Because a small gap between the rod and the cladding was developed by heating, the oxidation of uranium proceeded over a considerable area in spite of a small diameter of the pinhole. Remarkable swelling around the pinhole was observed at about 300 mg of weight gain by oxidation and burst of the cladding occurred when the weight gain reached to about 1, 000 mg.
The subjects of this series of experiments are (1) oxidation behavior, (2) oxidation rates of the intentionally punctured dummy fuel element, (3) diffusion coefficient of fission gas in the oxide powder, (4) correlation of oxidation with fission gas release, and (5) oxidation by decomposed carbon dioxide.
The results obtaained in these experiments are scheduled to be reported successively.抄録全体を表示PDF形式でダウンロード (2528K) -
平山 省一, 八劒 達雄, 天野 昇1963 年 5 巻 4 号 p. 316-324
発行日: 1963/04/30
公開日: 2009/03/26
ジャーナル フリーJRR-3, (natural uranium-heavy watar moderated and cooled research reactor) went critical on Sep. 12 in 1962, and at present measurements are being made of its characteristics at low power. The measured data will be compared in detail with design calculations, and the full power of 10 MW thermal is expected to be attained during 1964.
Preliminary design study for JRR-3 started in 1954, when for the first time in Japan budgetary appropriation was made for research and development in atomic enargy. Since 1956, work on JRR-3 has been under the charge of JAERI. Detailed design began in April 1957 with the cooperation of Japanese industrial companies. Construction work started in the beginning of 1959. Some problems encountered during these 6 years are described in this paper.抄録全体を表示PDF形式でダウンロード (657K) -
石森 富太郎, 渡辺 賢寿, 富村 和夫, 松本 初夫1963 年 5 巻 4 号 p. 325-332
発行日: 1963/04/30
公開日: 2009/03/26
ジャーナル フリーA fiberglass reinforced plastic (FRP) glovebox is made for chemical studies of α-emitters after being tested for chemical corrosion, heat and fire resistance, decontamination, mechanical strength, air tightness and air flow pattern. The FRP box shows very good chemical resistance for many reagents except for concentrated sulfuric acid, acetone and chloroform. The body of the box shows enough resistivity for fire accident owing to the collapse of the beaker containing 100200 ml of organic solvent such as TBP, toluene or diethyl ether. However, the fire test also indicates that the function of glovebox is often lost by breakdown of attchments such as air filter, glove and exhaust pipe.抄録全体を表示PDF形式でダウンロード (3378K) -
1963 年 5 巻 4 号 p. 333-334
発行日: 1963/04/30
公開日: 2009/03/26
ジャーナル フリーPDF形式でダウンロード (149K) -
M. BENEDICT1963 年 5 巻 4 号 p. 335-339
発行日: 1963/04/30
公開日: 2009/03/26
ジャーナル フリーPDF形式でダウンロード (914K)
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