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14 巻, 3 号
選択された号の論文の5件中1～5を表示しています
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桂 幸昭, 品川 睦明1972 年 14 巻 3 号 p. 100-105
発行日: 1972/03/30
公開日: 2009/04/21
ジャーナル フリーUranium was synergically extracted with theonyltrifluoroacetone (TTA) and tetraphenylphosphonium chloride (TPPC). Maximum synergism was observed at pH 6.5 with 5×10-3M TTA and 2×10-3M TPPC. The relation between log D and log[L] revealed that the ratio of uranyl, TTA and TPPC was 1:4:2.
Uranyltribenzoate, formed in benzoate-benzoic acid media, was also synergically extracted with TTA and TPPC. Maximum synergism was observed at pH 3 with 5×10-3M TTA, 2×10-3M TPPC and 5×10-3M sodium benzoate (NaB). The plot of log D and log[L] showed the ratio of uranyl, benzoate, TTA and TPPC to be 1:3:2:3.抄録全体を表示PDF形式でダウンロード (344K) -
池沢 芳夫, 木谷 進, 吉田 芳和, 狐塚 正夫, 武田 隼人1972 年 14 巻 3 号 p. 106-112
発行日: 1972/03/30
公開日: 2009/04/21
ジャーナル フリーThis experimental study has been performed to obtain fundamental data for in situ tests of activated charcoal filters installed in reactor exhaust systems using "R-112" as a tracer.
The results have shown that the leakage flow less than 0.1% by channelings around gasket seals and the defects caused by settling in activated charcoal filters could be evaluated by analyzing the "R-112" adsorption efficiency curves. Moreover, it was found that the very high adsorption of "R-112" tracer on activated charcoal (more than 99.995%) was not affected by in situ test conditions such as temperature, humidity, flow velocity. These results agreed with those determined by the theoretical calculation, assuming that mass transfer through a gas film was the controlling factor in adsorption of "R-112" by activated charcoal.抄録全体を表示PDF形式でダウンロード (419K) -
池本 一郎, 吉舗 信也, 竹下 寿英1972 年 14 巻 3 号 p. 113-123
発行日: 1972/03/30
公開日: 2009/04/21
ジャーナル フリーThe Enrico Fermi fast breeder reactor, reloaded with fresh fuel, again achieved criticality on July 18, 1970, following four years of repairs and modifications to remedy the limited fuel meltdown accident in October 1966. On October 16, 1970, the plant first attained its full licensed power level of 200MWt. The subsequent low-power and high-power nuclear test program was completed with a 5 day power demonstration run at the full licensed power level during the week of November 15, 1970.
Some 90 preloading, nuclear and plant monitoring tests covering all components and systems of the plant were prepared, conducted and evaluated. They include the performance tests of flow guards, (which were newly added to subassemblies to prevent any significant reduction of coolant flow by flat plate), of the malfunction detection analyzer (MDA), and of the delayed neutron detectors. The results of these tests were highly satisfactory.
Stable operation of the modified steam generator, the effectiveness of the. MDA for early warning of anomalous occurrences, and other results obtained should provide experience and data of great significance to the development, design, licensing and operation of future fast breeder reactor plants.
This paper summarizes the operating experience of the Fermi reactor up to 200MWt.抄録全体を表示PDF形式でダウンロード (750K) -
鈴木 進1972 年 14 巻 3 号 p. 124-130
発行日: 1972/03/30
公開日: 2009/04/21
ジャーナル フリーThe Second Plutonium Fuel Development Laboratory of the Power Reactor and Nuclear Fuel Development Corporation, which had been under construction since 1969, has now been completed, and production of Pu fuels for both FBR and ATR commenced in Feb. 1972. The total floor space is about 9, 000mm2 in which are housed separate production lines for FBR and ATR (pellet preparation, pin fabrication, assembling and recovery), as well as facilities for quality control fuel storage, air conditioning and management office. The annual production capacity is 5t and 3t for ATR and FBR, respectively. Some of the production facilities were equipped to operate automatically in order to reduce the risk of human radiation exposure. Systems for criticality control and material balance are described together with an outline of the arrangement of the facilities with fully equipped alarm system.抄録全体を表示PDF形式でダウンロード (5251K) -
田島 英三, 市川 龍資, 桑島 謙臣1972 年 14 巻 3 号 p. 131-137
発行日: 1972/03/30
公開日: 2009/04/21
ジャーナル フリーAn estimate is presented on the exposure of the Japanese population to environmental radioactivity from nuclear power plants and fuel reprocessing facilities. There are two main sources of radiation exposure to the population. Firstly, there is the contribution from the atmospheric 85Kr and hydrospheric 3H which originate from world-wide nuclear power production. The second component of population exposure derives from the atmospheric and coastal releases of both air-born and liquid radioactive wastes from nuclear facilities installed in Japan. Assuming that the nuclear power generating capacity of the whole world will be 4, 300GWe and that for Japan alone will be 220GWe in the year 2000, it is estimated that the above-mentioned exposure pathways will give rise to a dose rate of 1.7×104man-rem/yr for the Japanese population.抄録全体を表示PDF形式でダウンロード (498K)
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