Online ISSN : 1884-4111
Print ISSN : 0033-8303
ISSN-L : 0033-8303
Volume 14 , Issue 5
Showing 1-14 articles out of 14 articles from the selected issue
  • Tomihisa KAMBARA, Nobuyuki KASHIHIRA, Katsuyuki HAGITA, Chung-huei Ke
    1965 Volume 14 Issue 5 Pages 353-356
    Published: September 15, 1965
    Released: September 07, 2010
    Potassium antimonate was irradiated with thermal neutrons to investigate the distribution of recoil antimony atoms between the tri-and pentavalent states. The retention values were found to be decreased linearly with the decrease of the amounts of crystalline water in the compound. It may be supposed that the OH radical in the crystal may play an important role on the valence states of recoil antimony atoms.
    This supposition might be reasonable as compared with the results obtained for the antimony exchange reaction in a heterogeneous system (liq.-solid system) .
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  • Nagao IKEDA, Yoji KONDO, Hiroshi YAMASHITA
    1965 Volume 14 Issue 5 Pages 357-362
    Published: September 15, 1965
    Released: September 07, 2010
    The contents of lanthanum, samarium, europium and scandium were determined in several hot springs in Nasu and Kusatsu areas by the aid of the radioactivation method. The mixed hydroxides precipitated from 1-2l of the spring water were ignited and then subjected to the neutron irradiation in the JRR-1 reactor for 5 hrs. The total rare earth elements fraction was separated chemically and the radioactivity was measured with the single channel γ-ray spectrometer. These elements are present in five springs tested in the range of 1.2-5.7μg La/l, 0.8-2.6 μg Sm/l, 0.2-0.6μg Eu/l and 0.5-3.3μg Sc/l. Distribution of these elements between the spring water and the sinter deposit of the “Moto-yu”spring, Nasu, was also investigated.
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  • Takeyoshi ASANO, Satoshi OKADA, Koh SAKAMOTO, Setsuo TANIGUCHI, Yasush ...
    1965 Volume 14 Issue 5 Pages 363-367
    Published: September 15, 1965
    Released: September 07, 2010
    The isotopic exchange reaction of lutetium between the uncomplexed lutetium ion and its EDTA complex has been kinetically studied in a pH region from 6.5 to 5.5 by using lutetium-177 as a tracer. The rate is proportional to the first order of the concentration of both uncomplexed lutetium and its EDTA complex. The dependence of hydrogen ion concentration on the rate is very complicated. In the pH region from 6.5 to 6.0, the rate is independent on the concentration of hydrogen ion, and in the pH region below 6.0, clearly dependent on the hydrogen ion concentration. It may be supposed, therefore, that a possible mechanism for the exchange reaction in neutral solution is a simple displacement of the lutetium from the chelate compound by a collision with an uncomplexed lutetium.
    The rate of exchange is given by the expression:
    R=2.2×10-2 [Lu-EDTAOH-2] [Lu3+] mole l-1⋅min-1.
    In acid solution, the acid catalized reaction may compete with the bimolecular reaction.
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  • Yasushi NISHIWAKI, Hiroshi KAWAI, Yoshihide HONDA, Yuichiro KIMURA, Hi ...
    1965 Volume 14 Issue 5 Pages 368-373
    Published: September 15, 1965
    Released: September 07, 2010
    In order to estimate the behaviour and the distribution of radionuclides in the suspended matter in marine environment, the accumulation and distribution of 55Fe, 59Fe, 60 Co and 89 Sr in the suspended matter in surface seawater sampled at Osaka Bay was studied experimentally by the fractional filtration using Toyo Filter Paper Type No.5A (average pore size 18μ) and four different types of Millipore Filters (Type OS, SM, RA, HA) with different pore sizes. Dry weights, organic and inorganic materials in each fraction were determined.
    The radioactive concentration of the seawater was adjusted to about 10-4μc/ml for each nuclide. The results obtained were as follows:
    (1) The accumulation of the radioactive nuclides by the suspended matters was observed to reach an equilibrium in about 7-10 days.
    (2) The greatest concentration factors per dry weight of radionuclides were obtained in the fraction of large particle sizes recovered by the Toyo Filter Paper Type No.5A. (mean pore size 18μ), rather than in the fractions of relatively small particle sizes.
    (3) The distribution of radionuclides in each fraction indicated the tendency that the stronger activity of 60Co was observed in the fraction of large particle sizes, while that of 55Fe in the fraction of small particle sizes.
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  • Yoshiaki MARUYAMA, Kazuhide IDENAWA, Teruo MANRI
    1965 Volume 14 Issue 5 Pages 374-376
    Published: September 15, 1965
    Released: September 07, 2010
    Air-dry and wet cation exchange resins, Diaion SK#I1, were irradiated in the H-form, Li-form, Mn-form, Cd-form and Pb-form by the TRIGA-II reactor at 100 kW and air-dry anion exchange resins, Diaion SA#100, were irradiated in I-form and BO3-form. The exchange capacity losses of these resins were measured after irradiation and compared with those produced in the same resins by the 60Co γ-ray irradiation. Ferrous and cc erric dosimeters were employed to measure the absorbed doses.
    The exchange capacity losses of the H-form, Mn form and I-form resins by the reactor irradiation were in agreement with those obtained in the same form resins by the 60Co γ-ray irradiation. Their values of H-form, Mn-form and I-form resins by the reactor irradiation were 13.5, 10.8, 27.6% respectively at 3.3×108r. In the case of Cd form, Li-form and BO3-form resins attaching the elements which have large cross sections with thermal neutron or emit heavy charged particles at the moment of neutron capture, the damage of the resins by the reactor irradiation was larger than that obtained in the same form resins by the 60Coγ-ray irradiation. Their values of Cd-form, Li-form and BO3-form resins by the reactor irradiation were 18.0, 33.8, 43.8% respectively at 3.3×108r. Also the radiation damage of the resins immersed in water or 3N acetic acid solution was larger than that obtained in the air-dry resins by the reactor or the 60Co-γ-ray irradiation.
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  • Kazuta KITAHARA, Yoshimasa TANAKA, Akira KOYANO, Toshi YAGISAWA
    1965 Volume 14 Issue 5 Pages 377-381
    Published: September 15, 1965
    Released: September 07, 2010
    This study has been carried out to devise a new dose rate-meter base on the measurement of electric resistance of liquid organic compounds.
    A 16, 000 curie Co-60 source in the Japan Atomic Energy Research Institute was used as a radiation source.
    Electric resistance during irradiation was measured with a special type of measuring cell possessing wide electrodes and glass tape as insulator, devised by the present authors.
    It was found that a correlation between the dose rate I (r/hr) and the electric resistance R (MΩ) of the measuring cell enclosing liquid paraffin during irradiation could be expressed by the following formula, I=K/Rn (where K is a constant) at a constant temperature within a range of dose rate of 104 to 106 r/hr, but that electric resistance returned to the preirradiation level within a few hours upon the removal of the irradiation source, and re-irradiation gave the same electric resistance.
    From these facts it is considered that the special cell enclosing liquid paraffin could be applied for measuring a high dose rate.
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  • Kazushige TSUKUI
    1965 Volume 14 Issue 5 Pages 382-389
    Published: September 15, 1965
    Released: September 07, 2010
    Radioactive sources which are easy to convey and deal with, have now been developed by using porous glass.
    The followings are required as standard sources for β-and γ-ray measuring instruments and radioactive sources for industrial and medical instruments:
    No change in quality of radioactive material, no rupture of the radioactive sources, no release of radioactive material and easy preparation method of these sources.
    Material: Porous glass (SiO2 96%, B2O3 4%, void space 20%) was obtained from Toshiba Kasei Co., Ltd. and was used after treatment according to the usual method.
    Radioactive materials (137Cs, 60Co 90Sr, 204Tl) were obtained commercially from the Oak Ridge National Laboratory.
    Procedure: Procedure is quite simple, consisting essentially of three steps. First, a piece of sample (about 5mmφ×15mm) of porous glass was dipped for 5-24hrs in radioactive material solution of various concentrations. Secondly, the sample which has absorbed radioactive materials was washed in water. Then, the absorbed moisture was removed completely by gentle heating in a warm place. Thirdly, and lastly, this sample glass was shrunk at about 1, 000°C for 10 hrs. At this step, the glass radioactive source became a kind of sealed source, which depended on the fact that the porosity of glass surface was lost by heating treatment.
    Results and Discussion: Relation between radioactivity concentration of the radioisotope (137Cs, 60Co, 90Sr, 204Tl) solution and the absorbed radioactivity in glass was investigated in detail. In this case, when the radioactivity concentration of radioisotope in hydrochloric, nitric or sulfuric acid solution increased, the absorbed quantities of radioactive material per one gram of porous glass increased. And its amounts were directly proportional to the activity concentration of the radioisotope solution. This relation was checked up to 10c/ml of radioactivity concentration of solution.
    The absorbed quantities of radioisotope are investigated too as a function of the hydrochloric acid acidity in the radioisotope solution used. Accordingly, it is clear that the concentration of acid in radioisotope solution have an effect on the absorption of radioactive material for the porous glass.
    The absorbed quantities of radioactive material per one gram of porous glass have not any relation to the weight and shape of porous glass used. If the quality of glass is equal, therefore, the amounts of the absorption of radioactivity depend on only the volume of glass.
    Lastly, it was found that when the glass which absorbed radioactive material was shrunk at a high temperature, the glass radioactive sources were stable chemically and physically and in boiling test, the release of radioactive material was almost negligible. The shrinkage of porous glass by heat treatment was about 13v%.
    As has been mentioned, by the absorption of radioactive material into the porous glass, the radioactive sealed sources in an optional form and intensity were easily obtained.
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  • Michio ENDO, Masaaki HAZUE
    1965 Volume 14 Issue 5 Pages 390-399
    Published: September 15, 1965
    Released: September 07, 2010
    In a heating process of hot stripping with an oil firing heating furnace, sulphur components in fuel heavy oil are oxidized to sulphur dioxide.
    It is generally considered that sulphur dioxide in the combustion gas reacts on the heated steel by absorption and/or chemical reaction to give some influences on the sulphur content which affects the chemical and mechanical properties of rolled product.
    The purpose of this work is to determine the degree of migration of sulphur component from atmosphere to heated steel, to explain a possibility and limitation of use of “high sulphur oil” as fuel in the steel heating process.
    The migration of sulphur component which is supplied in the form of sulphur dioxide was investigated by a model experiment using sulphur-35 as a tracer at the following variables of the experimental condition; (1) sulphur dioxide concentration, (2) temperature, (3) heating time and (4) composition of atmosphere. The depth of diffusion of sulphur component which was originated from atmosphere was also investigated.
    Above 50% of sulphur component in atmospheric gas was observed to be dombined with steel species after being heated to 1, 200°C for one hour in an atmospheric gas including 0.14% sulphur dioxide.
    The steel species, however, lost most of their radioactivity by a surface treatment with an ammoniacal ammonium citrate solution to indicate the greater fraction of migrated sulphur had existed in oxidized layer (scale layer) on the surface.
    The amount and distribution of migrated sulphur in the scale and steel layer appear to be very affected by concentration of sulphur dioxide in atmosphere, heating temperature and heating time.
    The depth of diffusion of sulphur component into the non oxidized steel layer, measured autoradiographically, was observed to be about 0.14 mm after being heated at 1, 200°C for one hour, and it seems that the heigher the heating temperature was and the longer the heating time was, the deeper the diffusion depth is.
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  • Shigeru AONUMA, Tadanori MAYUMI, Masatada AOKI, YOKO KITAGAWA
    1965 Volume 14 Issue 5 Pages 400-405
    Published: September 15, 1965
    Released: September 07, 2010
    It has previously been shown in this laboratory that anserine was demonstrated as one of the effective substances of heart hormones.
    The present investigation was undertaken in order to establish quantitative and qualitative analysis o f anserine and carnosine, and to determine whether anserine and carnosine were directly biosynthesized from β-alanine or not. We also studied on specificity in rat organs.
    The following results were obtained,
    1) Injected β-alanine-2-14C was chiefly incorporated into adrenal and prostate.
    2) The incorporated β-alanine-2-14C was almost detected in anserine and carnosine fractions.
    3) Generally, anserine and carnosine in organs and urine could be fairly biosynthesized from β-alanine.
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  • Taiji SCHIMIZU, Saburo ABE
    1965 Volume 14 Issue 5 Pages 406-410
    Published: September 15, 1965
    Released: September 07, 2010
    The method of isolation of the nuclei from Ehrlich ascites tumor cells was reported and the metabolic activity of the isolated nuclei was investigated. It was shown that 3H-uridine, 3H-cytidine and 3H-guanosine were phosphorylated to nucleotides and incorporated into the RNA of nuclei when they were incubated with the isolated nuclei. 3H-Adenosine was not phosphorylated and 14C-orotic acid was not converted to uridylic acid by nuclei. They were not taken up by the RNA of nuclei. 14C-Glycine incorporated into the proteins of nuclei when it was incubated with nuclei. Thus, the nuclei isolated from ascites tumor cells were found to maintain the enzymic activity to synthesize RNA and proteins.
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  • Sudamoy BISWAS, Koji YAMAMOTO, Yoshimasa SATO, Yasuo UKAI, Yoshiro ONO ...
    1965 Volume 14 Issue 5 Pages 411-421
    Published: September 15, 1965
    Released: September 07, 2010
    Experiments on the protective effects of chemicals against radiation-induced damages in crop plants were carried out under both controlled conditions of temperature and field conditions. Different chemicals from the groups of inorganic and organic reducing substances, sulfhydryl containing compound, amine, vitamin, chelating agent, metabolite and other compounds were used.
    It was observed that the X-ray induced physiological damage was protected with cysteine, ferrous sulfate, vitamin C or Na-ascorbate, EDTA-2 Na and K-compounds in the pretreatment only. ATP was also effective in some conditions.
    Chromosome aberrations induced by radiation was reduced by K-compound, cysteine and reducing agents in both of pre-and post-treatment. Among them, reducing agents and cysteine decreased the number of chromosome bridges proportionally to that of fragments in the stage of anaphase to telophase in the 1 st mitotic cell divisions. On the other hand, K-compounds decreased more the number of fragments than that of bridges.
    Alost of chemicals used revealed no protective effects on radiation-induced sterility. Radiation-induced chlorophyll mutation frequencies were also scarcely affected by the treatment with chemicals in both cases of frequency of streaks on the leaves of X1 seedlings of heterozygous strains and that of chlorophyll mutations in X2 generations of homozygous varieties of barley and rice.
    As the results, it is concluded that the physiological damages, chromosomal aberrations, sterility and mutations induced by radiation may be occurred in different processes of the lining materials alter irradiation.
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  • Eiichi Ogawa, Shiro Suzuki, Hiroshi Tsuzuki
    1965 Volume 14 Issue 5 Pages 422-427
    Published: September 15, 1965
    Released: September 07, 2010
    Mice were preliminarily injected with 85Sr, and after a given time they were sacrificed, the femurs were taken out, placed in test tubes and their radioactivity (A1) was determined in a well-type scintillation counter. Then the femurs were incubated in various media with or without addition of drug, and after a given time, the radioactivity of the medium (A2) was determined.
    85Sr elution rate (%) was computed by A2/A1×100, and using this the affinity of 85Sr with bone was assessed. Further, effects of various drugs—chelating agents and salts—on elution of 85Sr were investigated.
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  • [in Japanese], [in Japanese]
    1965 Volume 14 Issue 5 Pages 428-438
    Published: September 15, 1965
    Released: July 21, 2010
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  • 1965 Volume 14 Issue 5 Pages A493-A176
    Published: September 15, 1965
    Released: July 21, 2010
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