Journal of Nuclear Science and Technology
Online ISSN : 1881-1248
Print ISSN : 0022-3131
Volume 25, Issue 11
Displaying 1-9 of 9 articles from this issue
  • Takaya SEKO, Daniel R. WILKINS, Shigemi SUGINO, Jiro KANI
    1988 Volume 25 Issue 11 Pages 837-847
    Published: November 25, 1988
    Released on J-STAGE: May 14, 2008
    JOURNAL FREE ACCESS
    The Advanced Boiling Water Reactor (ABWR) has been developed by an international team of BWR manufacturers to respond to worldwide utility needs in the 1990's. Major objectives of the ABWR program are design simplification; improved safety and reliability ; reduced construction, fuel and operating costs ; improved maneuverability ; and reduced radiation exposure and radwaste. The ABWR is the result of the continuing evolution of the BWR, incorporating state-of-the-art technology and improvements based on worldwide experience, and extensive design and test and development programs. The ABWR incorporates the best proven features from BWR designs in Japan, the United States and Europe. The many new features are seen to provide superiority in terms of performance characteristics and economics relative to current LWR designs. The Tokyo Electric Power Co., Inc. recently announced the selection of General Electric Co., Hitachi, Ltd. and Toshiba Corp. to design and construct two lead Advanced Boiling Water Reactors as Unit 6 and 7 at the Kashiwazaki Kariwa Nuclear Power Station. Construction is scheduled for the early 1990's, and commercial operation planned for 1996 for Unit 6 and 1998 for Unit 7.
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  • Shigeru YAMAGISHI, Yoshihisa TAKAHASHI
    1988 Volume 25 Issue 11 Pages 848-856
    Published: November 25, 1988
    Released on J-STAGE: May 14, 2008
    JOURNAL FREE ACCESS
    The conditions for preparing ThO2-UO3 sol by using the gaseous ammonia addition method are studied. Dependences of colloid particle size and colloid fraction of sol on U content, (Th+U) concentration and ammonia addition mode are observed, and the conditions for preparing sols suitable for gelation in CCI4-ammonia media are found in the range of 1.01.3 mol (Th+U)/l and U content of 030%. Using the resultant sols, the effect of sol concentration on gelation behaviors such as sphericity and cracking is clarified.
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  • Ichiro YAMAMOTO, Akira MATSUO, Akira KANAGAWA
    1988 Volume 25 Issue 11 Pages 857-867
    Published: November 25, 1988
    Released on J-STAGE: May 14, 2008
    JOURNAL FREE ACCESS
    The Chapman-Cowling (CC) formula as well as the Monchick-Sandler-Mason (MSM) formula for the thermal diffusion factor for H2-HT gas mixture were examined through separative analysis by comparing experimental results of isotope separation using thermal diffusion column. The CC formula could not explain quantitatively the thermal diffusion between H2 and HT, whatever parameters and/or intermolecular model potentials we chose. The Lennard-Jones (9-6) potential was regarded as the most adequate one among the model potentials tested here for H2-FIT gas mixture. The MSM formula was approximated so as to be evaluated even when input data for the formula are not available. The inelastic collision integral ratios were also estimated roughly in two ways. Application of the MSM formula could have reduced discrepancies between experimental and analytical results although the estimates of the formula and the inelastic collision integral ratios were rough.
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  • Tetsuya MATSUI, Haruo FUJIMORI, Kazumichi SUZUKI
    1988 Volume 25 Issue 11 Pages 868-874
    Published: November 25, 1988
    Released on J-STAGE: May 14, 2008
    JOURNAL FREE ACCESS
    The UO2+2 fluorescence spectra were measured for solutions simulating the raffinate of the codecontamination process in nuclear fuel reprocessing plants, including 27 kinds of coexisting ionic species. When the coexisting ion concentration was equal to that of the raffinate, the U concentration was determined in the range of 2100 mg/dm3 and detection sensitivity was only 1/6 that in the reference solution containing no coexisting ions. The UO2+2 fluorescence intensity decreased with increasing coexisting ion concentrations for the following three reasons.
    The first was absorption of the excitation beam by these ions. The second was absorption of fluorescence by these ions. The last was fluorescence quenching by interactions between UO2+2 and the coexisting ions. The respective ratios of fluorescence reduction attributed to these reasons at the raffinate were estimated as 0.26, 0.87 and 0.59, based on comparison of experimental results with calculations for absorption of the excitation beam and fluorescence.
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  • Takashi SHIROTANI
    1988 Volume 25 Issue 11 Pages 875-883
    Published: November 25, 1988
    Released on J-STAGE: May 14, 2008
    JOURNAL FREE ACCESS
    A realistic torso phantom with average body size of Japanese adult males has been developed for the calibration of counting systems used for in-vivo measurements of plutonium and other actinides. The phantom contains removable model organs (lungs, liver, kidneys and heart), model trachea and artificial rib cage, and also includes chest plates that can be placed over the chest to simulate wide range adipose/muscle ratio in the human chest.
    Tissue substitutes used in the phantom were made of polyurethane with different concentrations of ester of phosphoric acid. Model lungs were made of foamed polyurethane with small quantities of the additive, and the artificial rib cage was made of epoxy resin with calcium carbonate. The experimental data have shown that the phantom can be used as a standard phantom for the calibration.
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  • On the Basis of Parallel Irradiations
    Istvan VIDOVSZKY
    1988 Volume 25 Issue 11 Pages 884-888
    Published: November 25, 1988
    Released on J-STAGE: May 14, 2008
    JOURNAL FREE ACCESS
    To get information about the neutron spectrum in low enriched UO2-H2O lattices, the spectral indices SI(U8c/Dy) and SI(U8c/U5f) were measured on the basis of the parallel irradiation technique, which basically irradiates activation foils both in a neutron field to be investigated and in a reference field of thermal neutrons. In the present study, a fuel pellet of UO2 was used for the, measurement of activities caused by the neutron capture of 238U and the fission of 235U. Besides the technical details of the measurements, the origins of experimental errors are listed with the method how to eliminate them. The measurements were carried out in lattices of different fuel enrichment to demonstrate the capability of the present method, and the experimental results were compared with the calculated ones. It was found that the results of the present measurements are useful to assess the validity of the cell calculations.
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  • Kazuo FURUTA, Shunsuke KONDO
    1988 Volume 25 Issue 11 Pages 889-890
    Published: November 25, 1988
    Released on J-STAGE: May 14, 2008
    JOURNAL FREE ACCESS
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  • Satoshi YANAGIHARA, Shinsuke ASHIDA, Hozumi USUI
    1988 Volume 25 Issue 11 Pages 891-894
    Published: November 25, 1988
    Released on J-STAGE: May 14, 2008
    JOURNAL FREE ACCESS
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  • Satoshi FUKADA, Shoichi KITAJIMA, Nobuo MITSUISHI
    1988 Volume 25 Issue 11 Pages 895-897
    Published: November 25, 1988
    Released on J-STAGE: May 14, 2008
    JOURNAL FREE ACCESS
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