巻号一覧
後続誌
11 巻, 2 号
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海水ウラン採取のための吸着剤尾方 昇, 垣花 秀武1969 年 11 巻 2 号 p. 82-87
発行日: 1969/02/28
公開日: 2010/04/19
ジャーナル フリーAbout fifty insoluble compounds of titanium, aluminium, magnesium, calcium, silicon, zinc, chromium, lead and tin were examined in a search for suitable adsorbents of uranium in sea water. The only materials that exhibited an effective uptake were titanium hydroxide, lead sulfide and chromium hydroxide, the uptake capacities of which were 196, 134 and 68μg/g, respectively. While their uptake capacity was small, manganese dioxide, zinc hydroxide and lead hydroxide also adsorbed uranium in the pH range of sea water. Ferric hydroxide, ferrous sulfide, ferric phosphate, tin sulfide, titanium hydroxide and manganese oxide were found fo be good adsorbents in acidified sea wafer, though acidification of sea wafer would not be practical in indusfrial scale operations. Tannic acid salts of magnesium, calcium and titanium adsorbed uranium in sea water, but had the drawback of relatively large solubility.抄録全体を表示PDF形式でダウンロード (365K) -
早坂 秀雄, 武田 征一1969 年 11 巻 2 号 p. 87-95
発行日: 1969/02/28
公開日: 2010/04/19
ジャーナル フリーRecycling patterns and the long-time behavior of Th-U-Pu fast breeders have been investigated. The basic cycle adopted was to charge fertile materials (232Th, 238U) into both core and blanket, to sell a portion γB of the fissile materials (233U, 239Pu) formed in the blanket, and to recharge the remaining 1-γB into core. Of the fuel produced fuel in the core a part γC is sold in the market.
In this fuel cycle, γB and γC are either time dependent variables or else constant, so that four alternative recycling patterns were considered with different combinations of these factors. To facilitate the procedures of refabrication and estimation of Doppler effect, the system is controlled in such manner as to let the charging ratio into core and the composition ratio of 232Th and 238U in blanket be both constant.
The burnup equations for these recycling patterns have been derived as linear and non-linear differential equations. Breeding rates can be determined by solving the eigenvalue problems of these burnup equations.抄録全体を表示PDF形式でダウンロード (477K) -
三島 良績, 石野 栞1969 年 11 巻 2 号 p. 96-105
発行日: 1969/02/28
公開日: 2010/04/19
ジャーナル フリーThe production of inert gases by irradiation gives rise to various consequential effects on reactor materials such as swelling, fission product release and high temperature embrittlement. A review is presented on the production and the behavior of inert gases in reactor materials. Special emphasis is placed on the behavior of gas bubbles in solids. Studies in this field should be indispensable, for example, in raising the burnup attainable with metallic fuels and in preventing high-temperature embrittlement in FBR fuel cladding materials.
The article first covers the production of gas atoms by irradiation, and proceeds to a discussion of gas atoms in "as irradiated" condition. Further, the nucleation and growth of gas bubbles is treated, and attention is drawn to the importance of the role of vacancies. The migration of bubbles especially under various generalized forces is discussed. Finally, reference is made to the effects of gas bubbles in three typical cases, i.e. in metallic fuels, in UO2 and in stainless steels. Several principles that have been adopted to minimize swelling are also discussed.抄録全体を表示PDF形式でダウンロード (5333K) -
J.D. ORNDOFF, 清瀬 量平1969 年 11 巻 2 号 p. 106-110
発行日: 1969/02/28
公開日: 2010/04/19
ジャーナル フリーPDF形式でダウンロード (7998K) -
新井 義男1969 年 11 巻 2 号 p. 111-119
発行日: 1969/02/28
公開日: 2010/04/19
ジャーナル フリーPDF形式でダウンロード (2828K)
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