Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
Online ISSN : 2186-5256
Print ISSN : 0004-7120
ISSN-L : 0004-7120
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Volume 41, Issue 3
Displaying 1-6 of 6 articles from this issue
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  • Nuclear Technology and Society
    1999 Volume 41 Issue 3 Pages 147-173
    Published: March 30, 1999
    Released on J-STAGE: April 19, 2010
    DOIhttps://doi.org/10.3327/jaesj.41.147
    JOURNAL FREE ACCESS
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  • Development of the Accident Simulation System 'IMPACT' for Light Water Nuclear Power Plants
    Masanori NAITOH, Yasumasa ANDO, Hiroshi UJITA
    1999 Volume 41 Issue 3 Pages 174-201
    Published: March 30, 1999
    Released on J-STAGE: April 19, 2010
    DOIhttps://doi.org/10.3327/jaesj.41.174
    JOURNAL FREE ACCESS
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  • Clarification of Complex Phenomena in Nuclear Plants
    Present Status and Future Trend of Fluid Analysis by Cellular Automaton Methods
    Yasuyoshi KATO
    1999 Volume 41 Issue 3 Pages 202-218
    Published: March 30, 1999
    Released on J-STAGE: April 19, 2010
    DOIhttps://doi.org/10.3327/jaesj.41.202
    JOURNAL FREE ACCESS
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    Since most of complex phenomena comprise of various elementary processes e.g., fluid flow, heat conduction, phase transition, chemical reaction, structural deformation, and these processes interact each other nonlinearly, the complex phenomena cannot be easily clarified by such the conventional topdown approaches as describe phenomena by using differential equations. In contrast to the topdown approaches where the differential equations are located at the top of the analysis procedures, there are bottomup approaches where phenomena are reproduced by local interaction of particles or cells. Cellular automata are one of the typical bottomup approaches. The basic principle, computer simulation results, and massively parallel processors for the cellular automata are reviewed and perspectives of the bottomup approach are discussed on clarification of the complex phenomena in nuclear plants. The computer simulations mainly deal with fluid flows and phase interfacial phenomena.
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  • New Linkage of P & T (Partitioning and Transmutation) Treatment with Methodology of Geologic Disposal
    A Possible Breakthrough for Nuclear Technology in Tomorrow
    Asashi KITAMOTO
    1999 Volume 41 Issue 3 Pages 219-235
    Published: March 30, 1999
    Released on J-STAGE: April 19, 2010
    DOIhttps://doi.org/10.3327/jaesj.41.219
    JOURNAL FREE ACCESS
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  • Out-of-Pile Demonstration Test Program of Hydrogen Production System
    Coupling with HTTR
    Yoshiyuki INAGAKI, Tetsuaki TAKEDA, Tetsuo NISHIHARA, Kazuhiko HADA, K ...
    1999 Volume 41 Issue 3 Pages 250-257
    Published: March 30, 1999
    Released on J-STAGE: April 19, 2010
    DOIhttps://doi.org/10.3327/jaesj.41.250
    JOURNAL FREE ACCESS
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    Japan Atomic Energy Research Institute has been constructing a 30-MWt HTGR, named HTTR, to develop technology and to demonstrate effectiveness of high-temperature nuclear heat utilization. A hydrogen production system by natural gas steam reforming is to be the first heat utilization system of the HTTR. This report describes an out-of-pile demonstration tests program required for hydrogen production system coupling with the HTTR. The demonstration tests are classified into three parts as follows; (1) an out-of-pile hydrogen production test to develop operational and control technologies and to demonstrate high-temperature components such as a steam reformer and so on under simulated operational conditions, (2) a material test of catalyst tube, which is the pressure boundary between coolant (helium gas) and process gases, to estimate the effect of corrosion and hydrogen embrittlement on material strength (Hastelloy XR), and (3) a hydrogen permeation test to estimate tritium transportation from reactor to produced hydrogen. As for the out-of-pile hydrogen production test, a 1/30-scale test equipment which simulates key components downstream from an intermediate heat exchanger of the HTTR is under construction aiming at completion in 2000. The catalyst tube material and hydrogen permeation tests have started and are to be continued to 2000.
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  • Development of Carborne Gamma-ray Survey System
    Ryuichi SAKAMOTO, Masahiro TSUTSUMI
    1999 Volume 41 Issue 3 Pages 258-265
    Published: March 30, 1999
    Released on J-STAGE: April 19, 2010
    DOIhttps://doi.org/10.3327/jaesj.41.258
    JOURNAL FREE ACCESS
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    A carborne γ-ray survey system was developed aiming at implementation of environmental radiation investigation in and around Chernobyl area after the accident. This system consists of a dose rate meter, a GPS and a personal computer, and acquires γ-ray dose rates and positional data using two serial ports of the computer. It is indispensable to acquire these two kinds of data simultaneously for carborne γ-ray survey in a large area. A feature of the system is to be able to get these data continuously by means of a simple programming. This system has been used in and around Chernobyl area for a few years, and it has worked without any troubles. The outline of this survey system, which is applicable for configuration of environmental radiation data acquisition system is reported with some results in Chernobyl.
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