巻号一覧
後続誌
2 巻, 8 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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西原 宏, 西原 英晃1960 年 2 巻 8 号 p. 451-459
発行日: 1960/08/30
公開日: 2009/02/12
ジャーナル フリーThe stability of a boiling heavy water reacter is studied by the frequency response method.
The reactor type is the one analogous to that of HBWR (Halden Boiling Water Reactor), which is the only existing boiling heavy water reactor. For the most part, the sample reactor is based on the published design conditions of HBWR. Sinusoidal neutron distribution along the axial direction and uniform distribution in the radial direction are assumed.
The linearized power-reactivity feedback function first developed by E. S. Beckjord, et al. is modified and applied to our model. The power-reactivity transfer functions of the models with the metallic U loading and the UO2 loading are calculated for various operational conditions to investigate the stability.
It is concluded that the UO2 loading model is quite stable under the assumed conditions, and the metallic U loading model can also be made stable at very high power.抄録全体を表示PDF形式でダウンロード (450K) -
西土井 睦, 伊藤 益邦, 山本 寛1960 年 2 巻 8 号 p. 460-467
発行日: 1960/08/30
公開日: 2009/02/12
ジャーナル フリーWe had studied the treatment of the low level radioactive wastes with the electrodialysis employing ion exchange membranes as a process to treat them economically. It was found that electrodialyzer JAERI-300B as lonics unit had good properties for demineralizing brine water, and was applied for the treatment of actual radioactive wastes.
From our experiments, it was concluded that the transfer rate of either non radioactive or radioactive ions through ion exchange membrane was nearly equal, and resulted that electrodialyzer require no special modification for treating of the radioactive wastes, if we combine it into the treatment plant operating now at JAERI. In two stage treatment the concentration of concentrated effluent from the electrodialyzer rises up to 100 times of initial feed, so that the evaporating cost reduces markedly and at the same time the concentration of demineralized effluent decreases to one-tenth, and so the volume of break through from final ion exchange tower, viz., the ratio (break through volume to volume of regeneration waste) increases ten times.
We found that the power for the electrodialysis was only 1kWH/m3 when demineralizing from 2, 000ppm to 20ppm, and the over all power including three pumps for feed, circulate and discharge was only 10kWH/m3.
The current efficiency of this electrodialyzer was over 70%抄録全体を表示PDF形式でダウンロード (2406K) -
ループの水化学野村 末雄1960 年 2 巻 8 号 p. 468-473
発行日: 1960/08/30
公開日: 2009/02/12
ジャーナル フリーInduced activity and change of various properties, such as electric conductivity, pH value and oxidation potential, of loop water in our in-pile corrosion test loop are measured and analized.
The activity of loop water is found to be mainly caused by 16N under reactor operation but γ rays from 64Cu and 56Mn dissolved in water become powerful after reactor shut down.
Electric conductivity of continuously demineralized water in the loop fluctuates with the reactor operating power, but that of non-demineralized water decreases with time and do not return to its initial value even after reactor shut down.
The pH value of loop water is not so much affected by fluid condition or reactor condition, and the oxidation potential of loop water at 50°C drops or rises under reactor irradiation whether the water is continuously demineralized or not.
Amount of dissolved oxygen in water and of hydrogen generated from water are also measured, and H2O2 which is expected to be generated by radiolysis of loop water is not detected in flowing water at 70°C under reator operation.抄録全体を表示PDF形式でダウンロード (339K) -
法橋 登, 北爪 光幸1960 年 2 巻 8 号 p. 474-477
発行日: 1960/08/30
公開日: 2009/02/12
ジャーナル フリーThe expression for the intensity of gamma radiation which is generated in an infinite slab shield due to thermal neutron capture and escapes across the front and rear faces of the material is obtained for given fast and thermal neutron currents incident on the shield. The result is based on the two group approximation for the thermal neutron distribution and is a natural extension of lliffe's result which does not take the incident fast neutron into account.抄録全体を表示PDF形式でダウンロード (143K) -
梅沢 弘一1960 年 2 巻 8 号 p. 478-482
発行日: 1960/08/30
公開日: 2009/02/12
ジャーナル フリーTri-n-butyl Phosphine Oxide (TBPO)の四塩化炭素溶液と硝酸の系において, TBPOの濃度1×10-4Mから3×10-1M, 硝酸濃度0.5Mから10Mの範囲にわたってPu (IV)とPu(II)の分配平衡が測定された。その結果,ウラン濃度が0.005M以下であれば中性子照射したウランからプルトニウムを容易に抽出できることが明らかになった。抄録全体を表示PDF形式でダウンロード (223K) -
大山 彰1960 年 2 巻 8 号 p. 483-492
発行日: 1960/08/30
公開日: 2009/02/12
ジャーナル フリーPDF形式でダウンロード (761K) -
1960 年 2 巻 8 号 p. 493-495
発行日: 1960/08/30
公開日: 2009/02/12
ジャーナル フリーPDF形式でダウンロード (159K)
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