巻号一覧
後続誌
1 巻, 6 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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深井 佑造1959 年 1 巻 6 号 p. 353-358
発行日: 1959/11/30
公開日: 2009/02/12
ジャーナル フリー一般にU-Al合金の板状燃料をもつ原子炉での共鳴を逃れる確率は均質化の取扱いをする。これはPに対して過小評価をしていることになっている。このような取扱いをする理由の1っには, U-Al合金燃料系の実効共鳴積分の実験式がないということがある。ここではU-Al合金の板状燃料と減速材との無限並列系でのPをInfinite Mass近似とScattering Model(これはNarrow Resonance近似である)とを用いて計算し比較した。従来の発表論文ではほとんどが数値解法をしているので,ここでは計算にあたってRoeの近似式等を用い,できる限り解析的に求めた。すなわちこの論文の目的は,
(1) U-Al合金系のPの計算が解析的に可能であること
(2) その数値結果からInfinite Mass近似とScattering Modelとの比較を示したものである。
実際の数値計算は東芝教育訓練用原子炉の炉心構造の場合について行なわれた。抄録全体を表示PDF形式でダウンロード (249K) -
宇梶 六夫, 蔭山 育造1959 年 1 巻 6 号 p. 359-362
発行日: 1959/11/30
公開日: 2009/02/12
ジャーナル フリーIn this report, the relationship between the hydrogen fluoride content in fluorine and the electric capacity change measured by variable condenser was theoretically a derived from Debye's formula concerning molecular polarization. The sample condenser, usad in this study, was made of poly tetrafluoroethylene resin. Its terminal was platinum, and the electric capacity was 200 PF. The liquid nitrogen and mercury method was used for the chemical analysis of hydrogen fluoride and fluorine in the samples. Concerning the relationnship between the hydrogen fluoride content (ω wt.%) and the electric capacity change (ΔCPF), the following equation was obtained;
ΔC=4.3×10-2
ω
The electric capacity of the variable condenser was 300 PF and the experimental accuracy was 0.06 PE抄録全体を表示PDF形式でダウンロード (195K) -
液状放射性廃棄物の蒸発処理三石 信雄, 阪田 貞弘, 松田 裕二, 山本 寛1959 年 1 巻 6 号 p. 363-369
発行日: 1959/11/30
公開日: 2009/02/12
ジャーナル フリーA large scale evaporation unit consisting of evaporator, cyclone and packed tower was constructed, with which studies were made of the liquid entrainment and its removal.
The results obtained are as follows
(1) The decontamination factor of the evaporator lies between 104 and 105.
(2) That of the cyclone is in the range of 10 to 102.
(3) The over-all decontamination factor of evaporation unit lies between 106 and 107.
(4) The optimum vapor mass velocity in the vapor space of the evaporator is about 2000kg/m2hr. With this optimum vapor mass velocity, the maximum over-all decontamination factor is obtained.
Furthermore, the results obtained by the large scale evaporation unit were compared with that obtained by the small scale evaporation unit.抄録全体を表示PDF形式でダウンロード (416K) -
ウラン燃料要素に関する研究, (4)武谷 清昭1959 年 1 巻 6 号 p. 370-375
発行日: 1959/11/30
公開日: 2009/02/12
ジャーナル フリーSpecial hoods for machine tools, such as lathe, grinding cutter and bench drill, are designed for machining natural uranium metal and these tools mounted with hood are used in metallurgy laboratory of Japan Atomic Energy Research Institute. The hoods mounted onto tool should be well ventillated to avoid contamination. Handling of tool is modified to be adequate for remote controlling for the purpose of minimizing the chances of opening the hood during operation, and to make the tool to be operated by machinist without any difficulty in spite of this modification. Collection of uranium chips contained in coolant is done in a filter vessel which is specially designed for easy taking out chips from the vessel, and transporting them to waste disposal plant. These are the main points which were considered in the design of special hoods for machining natural uranium metal. Experiences and operating data on these tools are also reported in this paper.抄録全体を表示PDF形式でダウンロード (866K) -
清水 彰直1959 年 1 巻 6 号 p. 376-384
発行日: 1959/11/30
公開日: 2009/02/12
ジャーナル フリーTwo forms of variational expressions are developed for the neutron energy spectrum and the effective reaction rate and its temperature coefficient in the thermal region with, “Monoatomic Heavy Gas Model”.
Using the first form of variational expressions, the author obtains the upper and lower limit of neutron thermal spectrum with the above mentioned model.
Next, the effective thermal cross-section and and its temperature coefficient are obtained as an extremum of functional in another form of variational expressions, and the limit of the validity of Neutron Temperature as a parameter expressing the deviation of spectrum from Maxwell distribution is discussed.抄録全体を表示PDF形式でダウンロード (430K) -
金沢 一雄1959 年 1 巻 6 号 p. 385-391
発行日: 1959/11/30
公開日: 2009/03/27
ジャーナル フリーThe oversize of 300mm may be rejected as waste from the high-grade ore containing 0.10.2%U3O8 and the oversize of 50mm may be rejected as waste from the low-grade ore containing 0.010.05%U308.
By rejecting these wastes containing less than 0.01% U3O8, the amount of feed for leaching will be reduced to about a half of that of the run of mine ore and the grade of the remained ore becomes about twice as that of the run of mine ore. The recovery of uranium may be more than 80%.
The uranium minerals which adhere to the surface of lump ores may be recovered by washing.抄録全体を表示PDF形式でダウンロード (380K) -
1959 年 1 巻 6 号 p. 392-394
発行日: 1959/11/30
公開日: 2009/02/12
ジャーナル フリーPDF形式でダウンロード (746K)
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