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6 巻, 1 号
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見塩 規行, 鴨志田 厚, 角谷 省三, 石原 健彦1964 年 6 巻 1 号 p. 2-7
発行日: 1964/01/30
公開日: 2009/03/26
ジャーナル フリーThe highly radioactive waste which arises from the processing of irradiated fuel is too hot to handle and hence, in current practice, is stored without treatment in underground tanks for hundreds years. Any means which would be able to remove 137Cs, one of the most harmful long half-lived components, from the liquid waste from fuel reprocessing are highly appreciated.
The authors have developed a special solid ion-exchange material of ferrocyanide-bentonite mixture (Ferrocyanide-Exchanger) made by a freezing-thawing method.
This new adsorption material has shown its capability of adsorbing Cs exclusively even from 6N nitric acid solution containing various other ions, and the authors have succeeded in separating 137Cs from synthetic Purex waste and Zirflex waste with this new material.
80% elution of 137Cs from this ferrocyanide-bentonite exchanger was accomplished by use of silver nitrate solutions.抄録全体を表示PDF形式でダウンロード (358K) -
門田 一雄, 三上 隆夫1964 年 6 巻 1 号 p. 7-15
発行日: 1964/01/30
公開日: 2009/03/26
ジャーナル フリーThe effective delayed neutron fraction of TTR-1 has been measured by the substitution technique. The poison plates were made of boron steel.
The changes in reactivity produced by the substitution of a poison plate for a fuel plate were measured by means of a calibrated control blade.
The sum of the reactivity changes associated with the substitution of all the fuel plates of reactor was Σiρi=136.6$.
The correction for the mismatch between the absorption cross-section of fuel and poison was made by using a 3 group diffusion equation.
The group constant and the fuel cross-section were obtained by codes MUFT and TEMPEST. The reactivity change due to the absorption cross-section mismatch was obtained by the perturbation calculation. The result was
Reactivity change due to absorption cross-section mismatch=0.0622.
From this value and from the result of measurements, the value of the effective delayed neutron fraction is given by
βeff=1+0.0622/136.6-1.2=0.00784抄録全体を表示PDF形式でダウンロード (646K) -
西 朋太, 藤原 一郎1964 年 6 巻 1 号 p. 15-20
発行日: 1964/01/30
公開日: 2009/03/26
ジャーナル フリーThe use of a new eluting agent, ammonium α-hydroxy·α-methyl-butyrate, for the separation of the lanthanide in cation-exchange chromatography was investigated. The new eluant has given better separation than ammonium α-hydroxy isobutyrate.
When ytterbium is taken as an arbitrary standard, separation factors are La 858, Ce 286, Pr 177, Nd 129, Pm 87.0, Sm 49.6, Eu 25.1, Gd 18.2, Tb 9.60, Dy 5.50, Ho 2.99, Er 2.30, Tm 1.35, Yb 1.00, Lu 0.415, Y 5.01 and Sc 0.188.抄録全体を表示PDF形式でダウンロード (330K) -
金川 昭, 高島 洋一1964 年 6 巻 1 号 p. 20-28
発行日: 1964/01/30
公開日: 2009/03/26
ジャーナル フリーBoth the separation factor and the separative power of a con-current gas centrifuge have been studied in relation to the gas feed rate and the effective length of the rotor. The differential equation of centrifugal separation through (n+1) cylindrical thin con-current streams has been drived, and solved in the cases of n=1 and 2.
The relations of the gas feed rate per length of the rotor to both the separation factor and the separative power have been compared with those in the case of counter-current flow which are varied with the ratio of length of rotor to the radius, as shown in Figs. 4 and 5.
It has been found that the gas feed rates in the counter-current flows need extremely less values than the con-current flow rates to get the identical separative power, however the gas circulating rates in the counter-current flow are comparable.
From the analysis of three cylindrical thin con-current streams, the influences of thickness of the streams upon the separation has been evaluated.抄録全体を表示PDF形式でダウンロード (494K) -
Zr, Zr合金の腐食野村 末雄, 伊藤 昇, 伊丹 宏治, 圷 長1964 年 6 巻 1 号 p. 28-36
発行日: 1964/01/30
公開日: 2009/03/26
ジャーナル フリーCorrosion and hydrogen pick-up of pure Zr, Zircaloy-2 and -4 were studied by high temperature and high pressure water loop in which sample coupons were immersed in flowing demineralized water at 260° and 280°C with velocities of 12.0 and 2.5m/sec. In most of experimental runs, two of corroding coupons were removed at each 100 hr of period and replaced with new ones. Total immersion time was limited to 400 hr at maximum, and a continuous run was carried out for a comparison to intermittent runs.
Weight gain vs. time curves for Zircaloy-2 at 260°C are different from those at 280°C in shape which weights of samples are gradually increase with time in the former although they are almost saturated at 100 hr in the latter.
Both the effects of water velocity and dissolved oxygen on corrosion are not remarkable, and sample replacement also shows little effect on corrosion rate.
Hydrogen pick-up vs. time curves are well correspond to weight gain vs. time curves at the same water conditions.
Pure Zr was found to be corroded more severe than Zircaloy-2 and shows break away of surface film after the definite period. Zircaloy-4 is similar in the oxidation behavior to Zircaloy-2 but not in the hydrogen pick-up which Zircaloy-4 shows a smaller amount of pick-up than Zircaloy-2.抄録全体を表示PDF形式でダウンロード (2354K) -
東郷 文雄, 高瀬 博1964 年 6 巻 1 号 p. 37-42
発行日: 1964/01/30
公開日: 2009/03/26
ジャーナル フリーThe result of uranium prospecting for economic development since 1963 has shown that Ningyô-tôgé and its vicinity on the boundary of Okayama and Tottori Prefs, the region composed of Misasa Group of Neogene Tertiary, have the industrial possibilities from the viewpoint of their grade and ore reserves. Ten uranium ore bodies or so were already found and their ore reserves were also grasped (ore reserves of each body: less than several hundreds thousand tons, their average grade: about 0.06% U3O8). It is said that this average grade is lower than those of foreign countries.
Recently, the continuous distribution of high-grade uranium ore body over 8, 000 m2 was discovered in the south gallery of Nakatsugo, Ningyô-tôgé mine where the intensive prospect by tunnelling had been put under way. It is confirmed that its average grade is 1%, the thickness of the mineralized layer is 0.65 m and the amount of uranium metal is more than 100 t. Such a rich uranium ore body is very in the world.
In this paper, the outline of this significant ore body is presented.抄録全体を表示PDF形式でダウンロード (469K) -
1964 年 6 巻 1 号 p. 43-44
発行日: 1964/01/30
公開日: 2009/03/26
ジャーナル フリーPDF形式でダウンロード (155K) -
A. CHAPPELIER1964 年 6 巻 1 号 p. 45-49
発行日: 1964/01/30
公開日: 2009/03/26
ジャーナル フリーPDF形式でダウンロード (422K) -
1964 年 6 巻 1 号 p. 49b
発行日: 1964年
公開日: 2009/03/26
ジャーナル フリーPDF形式でダウンロード (73K) -
1964 年 6 巻 1 号 p. 49a
発行日: 1964年
公開日: 2009/03/26
ジャーナル フリーPDF形式でダウンロード (73K)
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