巻号一覧
後続誌
8 巻, 1 号
選択された号の論文の11件中1～11を表示しています
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矢島 聖使, 亀本 雄一郎, 柴 是行, 半田 宗男1966 年 8 巻 1 号 p. 3-11
発行日: 1966/01/30
公開日: 2009/03/31
ジャーナル フリーAn inpile loop is described which is capable of continuously measuring the release of fission gas from ceramic fuels during irradiation in the Japan Research Reactor No.3.
The fuel specimen is heated to temperatures of up to 1, 000°C by the combined action of its own fission and a Pt wire heater.
The neutron flux for the specimens is controlled by changing the rod pattern and the reactor power. Specimens of about 22 mm diameter and of lengths up to 40 mm can be accommodated. A continuously flowing sweep gas (He gas) carries the fission gases outside the reactor where the radioactive isotopes are measured by γ-ray spectrometry. The non-radioactive gases released from the specimen during irradiation is determined continuously by an elusion gas chromatograph.抄録全体を表示PDF形式でダウンロード (6408K) -
田上 嵩, 北爪 光幸1966 年 8 巻 1 号 p. 12-15
発行日: 1966/01/30
公開日: 2009/03/31
ジャーナル フリーIn a water-shielded reactor, the photonuclear reaction γ(d, p) n takes place between γ-rays emitted from reactor core and deuterons contained in the shielding water surrounding the core. Photoneutrons produced by the reaction are distributed in the water layer in addition to the neutrons originated from the core.
In this report, it is shown that the distribution of the thermal photoneutron flux φγl in water not close to the core surface is apploximately given by the simple formula:
φγ=ΣiΣγni/Σ2/(1-μi2τ)(1-μi2L2)γi, (L2=D2/∑2)
where φiγ and μi represent the γ-ray flux in the i-th energy group and its linear absorption coefficient in water, ∑iγn is the macroscopic cross section for the photoreaction, D2 and ∑2 are the diffusion coefficient and the absorption cross section for thermal neutrons in water and √τ is the slowing-down length in water.
Comparison of the calculated results to the experiments in BSR-1 shows that the above formula reproduces the photoneutron distribution reasonably well in a region where the neutron flux originated from the reactor core is negligibly small. In particular the above expression for photoneutrons together with the calculated neutron flux originated from the core can explain a bend in the observed neutron flux distribution occuring at about 1.8 m from the core surface of BSR-1.抄録全体を表示PDF形式でダウンロード (2067K) -
岐美 格, 白滝 康次, 滝谷 紘一1966 年 8 巻 1 号 p. 16-24
発行日: 1966/01/30
公開日: 2009/03/31
ジャーナル フリーThe steam volume fraction of two phase mixture flowing upward under atmospheric pressure in the two vertical circular pipes of which inner diameters are 13.8 mm and 21.0 mm was measured, taking into consideration the flow patterns, with a capacitance type void meter.
The steam volume fraction and slip ratio vary with steam weight fraction (steam quality) χ in different fashions for different flow patterns. For example, the slip ratio increases with increasing the steam quality, but its slope decreases as the bubble flow (χ<0.1%) changes into slug flow (0.1%<χ<0.51%) and the slug flow into annular flow (χ>0.51%). The effect of superficial velocity V0 on slip ratio S is most significant in the region of annular flow, and S decreases as V0 increases from 30 cm/s to 100 cm/s.
For bubble flow, taking account of the effect of wake of bubbles, a theoretical equation to predict its slip ratio and steam volume fraction was derived. This equation satisfies not only the present experimental results but also the experimental data under high pressure obtained by several investigators. For slug flow, the present experimental results were compared with Moissis, et al.'s experiments which discussed the development of slug.抄録全体を表示PDF形式でダウンロード (718K) -
杉本 恵美子, 金子 正人, 安斎 育郎, 吉沢 康雄1966 年 8 巻 1 号 p. 25-27
発行日: 1966/01/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (250K) -
原子力直接発電研究専門委員会1966 年 8 巻 1 号 p. 28-35
発行日: 1966/01/30
公開日: 2009/03/31
ジャーナル フリーA Summery is given of the activities of the “Special Committee on Direct Conversion of Nuclear Energy to Electricity” in the two years from its establishment in October 1963 to its termination in September 1965. The review covers the present status of the studies undertaken and the technical problems involved are reviewed on magnetohydrodynamic power generation. The subjects reviewed include nonequilibrium ionization, electronic phenomena in the boundaries of electrodes, thermodynamic and fluid mechanical problems, liquid metal MHD power generation, high temperature materials, and technical problams relating to the development of MHD power generation plants. Problems concerning other conversion methods and the associated high temperature nuclear reactors will be reviewed in the following issue.抄録全体を表示PDF形式でダウンロード (754K) -
J. A. DENNIS1966 年 8 巻 1 号 p. 36-40
発行日: 1966/01/30
公開日: 2009/03/31
ジャーナル フリーThe activities at Harwell in neutron dosimetry can be considered to have passed through three distinct periods. From 1949 to 1951 various attempts were made to derive maximum permissible levels; from 1954 to 1958 instruments based on the 1955 ICRP recommendation were developed; and since 1959 the physical bases of the calculations are being experimentally verified and gaps in instrumentation filled.
In this paper, the work on neutron dosimetry at Harwell is described under the four headings of derivation of maximum permissible levels of neutron fluxes, the personnel dosimeter, the dose-rate meter, and measurement of neutron fluxes and absorbed doses.抄録全体を表示PDF形式でダウンロード (4722K) -
中村 康治1966 年 8 巻 1 号 p. 41-45
発行日: 1966/01/30
公開日: 2009/03/31
ジャーナル フリーIt is incontestable that plutonium fuel development is essential in determing nuclear fuel policy, especially in this country which has very few uranium resources and no diffusion plant, and consequently has to import enriched uranium. Japans plutonium development program must be pursed with the view to the use of this fuel in fast breeder reactors as well as in thermal reactors in order to economize the enriched uranium to be imported. The Plutonium Fuel Development Laboratory of the Atomic Fuel Corporation has now been completed and is embarking on work concerning plutonium handling. Some of the safety aspects of this facility are discussed in its relation to the fuel development program. Since mixed oxide fuel element fabrication based on vibratory compaction and sol-gel preparation of coarese and high density UO2-PuO2 particles have been chosen as the main processes to be utilized, the problem of plutonium containment presents less difficulties than in the case of metal or other pyrophoric compounds. Various kinds of safety equipment are installed, including a criticality warning system and fire protection. The safety system also includes a series of operating procedure manuals and criteria, and discipline demanded of laboratory personnel is discussed in brief.抄録全体を表示PDF形式でダウンロード (4903K) -
1966 年 8 巻 1 号 p. 46-47
発行日: 1966/01/30
公開日: 2009/03/31
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本島 健次1966 年 8 巻 1 号 p. 48-51
発行日: 1966/01/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (357K) -
1966 年 8 巻 1 号 p. 63a
発行日: 1966年
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (84K) -
1966 年 8 巻 1 号 p. 63b
発行日: 1966年
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (84K)
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