Kakuyūgō kenkyū
Online ISSN : 1884-9571
Print ISSN : 0451-2375
ISSN-L : 0451-2375
Volume 67, Issue 6
Displaying 1-14 of 14 articles from this issue
  • Akira Kohyama
    1992 Volume 67 Issue 6 Pages 485-489
    Published: June 25, 1992
    Released on J-STAGE: October 22, 2010
    JOURNAL FREE ACCESS
    The most important and difficult part of materials research for fusion reactor is realized to be irradiation studies of fusion reactor materials.Irradiation studies of fusion reactor materials utilizing FFTF/MOTA, as one of Japan/U.S.A.Fusion Collaboration Programs, have important role to establish fundamental understanding of heavy irradiation effects on materials behavior and properties and to develop methods and technologies for advanced irradiation studies under fusion reactor environment.This paper briefly reviews the history, the state of the art, and the future of the FFTF/MOTA program.
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  • Yutaka Kohno
    1992 Volume 67 Issue 6 Pages 490-496
    Published: June 25, 1992
    Released on J-STAGE: October 22, 2010
    JOURNAL FREE ACCESS
    R & D of heat resistant steels as structural materials for fusion reactor is one of the most important parts of fusion technology.This paper provides some of the recent results of heavy radiation effects on austenitic stainless steels, ferritic steels and reduced activation steels from FFTF cycle 10/MOTA-1F specimens with the emphasis on F82H reduced activation martensitic steel.Microstructural evolution and mechnical property changes are reviewed.
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  • Akihiko Kimura
    1992 Volume 67 Issue 6 Pages 497-500
    Published: June 25, 1992
    Released on J-STAGE: October 22, 2010
    JOURNAL FREE ACCESS
    Reduced activation is realized to be an important issue from reactor safety, maintenance, waste management and other view points.Low activation ferritic steels are potential options to this issue and heavy radiation effects on these materials have been an important part of FFTF/MOTA program.This paper provides effects of fast neutron irradiation in FFTF on mechanical property changes and microstructural evolution of some low activation ferritic steels developed for fusion.
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  • Heihichiro Takahashi
    1992 Volume 67 Issue 6 Pages 501-504
    Published: June 25, 1992
    Released on J-STAGE: October 22, 2010
    JOURNAL FREE ACCESS
    One of strategies for developing fusion reactor materials is to start from clear understandings of microstructural evolutions and of their mechanisms.The pure and model alloys group in FFTF/MOTA program cares for elementary and basic processes of radiation damage mainly from damage microstructural development.This paper provides recent results from MOTA program on austenitic steels.The importance of radiation induced segregation and radiation enhanced precipitation in microstructural evolution and phase stability is emphasized.
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  • Katsunori Abe
    1992 Volume 67 Issue 6 Pages 505-507
    Published: June 25, 1992
    Released on J-STAGE: October 22, 2010
    JOURNAL FREE ACCESS
    Neutron irradiation effects in molybdenum as high heat flux materials are surveyed. Microstructures including small dislocation loops, dislocations, voids and void lattices were developed depending on irradiation conditions.Neutron irradiation induced severe loss of ductility, but the degree of embrittlement depended on materials conditions.Radiation resistance of the metal may be improved by choosing proper heat treatment and fabrication method.
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  • Hideki Matsui
    1992 Volume 67 Issue 6 Pages 508-511
    Published: June 25, 1992
    Released on J-STAGE: October 22, 2010
    JOURNAL FREE ACCESS
    Vanadium alloys are expected to be potential reduced activation materials for fusion power reactors. R&D works of vanadium alloy have been emphasized in FFTF/MOTA program, where a new simulation irradiation technique, Dynamic Helium Charging Experiment (DHCE), has been developed.This paper provides recent results from FFTF/MOTA program with the emphasis of helium effects on swelling and on helium embrittlement.
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  • Takeo Muroga, Hiroshi Kawanishi, Somei Ohnuki
    1992 Volume 67 Issue 6 Pages 512-514
    Published: June 25, 1992
    Released on J-STAGE: October 22, 2010
    JOURNAL FREE ACCESS
    An overview is presented on the ongoing researches of synergistic effects of displacement damage and helium production in the FFTF/MOTA US-Japan collaboration studies. Outline of isotopically controlled boron addition studies and recent results are reviewed.
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  • Michio Iseki
    1992 Volume 67 Issue 6 Pages 515-518
    Published: June 25, 1992
    Released on J-STAGE: October 22, 2010
    JOURNAL FREE ACCESS
    Graphite and carbon-carbon composites or other carbide composites are considered to be candidate for plasma facing materials or structural material of fusion reactors because of their low atomic number, high thermal conductivity, stability under irradiation etc. This report briefly summarizes the mechanical properties, physical properties and microstructure changes of graphite, carbon composites and metal matrix composites after neutron irradiation. Generally, the effects of neutron irradiation are quite remarkable on physical properties of the graphite materials.
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  • Tatsuo Shikama, Shinji Sato
    1992 Volume 67 Issue 6 Pages 519-523
    Published: June 25, 1992
    Released on J-STAGE: October 22, 2010
    JOURNAL FREE ACCESS
    Materials handling techniques fbr highly radio-activated materials are key issues to accomplish post irradiation examinations (P. I. E. s) of heavily irradiated materials.To perform P. I. E. s of FFTF/MOTA irradiated specimens in hot-cells has been a technical challenge and many efforts to develop those techniques have been devoted. This paper describes status of the art of the techniques in Oarai Branch of IMR and hose developed in the frame work of the FFTF/MOTA program.
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  • Tetsuo Iguchi
    1992 Volume 67 Issue 6 Pages 524-529
    Published: June 25, 1992
    Released on J-STAGE: October 22, 2010
    JOURNAL FREE ACCESS
    Analysis of neutron irradiation environment is essentially required to make clear understanding of radiation effects on materials. Neutron dosimetry using activation technique is almost a unique solution to measure neutron fluence, neutron energy spectrum and related nuclear transmutation rates in heavy irradiation experiments. This paper provides an outline of neutron dosimetry technique applied to the FFTF/MOTA program, including a brief review on the Japan/U.S.A. collaboration research studies to improve the dosimetry accuracy.
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  • Yoshiharu Nakamura
    1992 Volume 67 Issue 6 Pages 530-538
    Published: June 25, 1992
    Released on J-STAGE: October 22, 2010
    JOURNAL FREE ACCESS
    Recent studies of nonlinear ion-acoustic waves in a multicomponent plasma with negative ions are described. When the density of the negative ions is less than, equal to and larger than a critical value, only positive, both positive and negative and only negative solitons, respectively, propagate. Those solitons are either Korteweg-de Vries (K-dV) solitons or modified K-dV solitons. Existence of large amplitude solitary waves is stated. Observations of envelope solitons given by the nonlinear Schrodinger equation are reviewed.
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  • 1992 Volume 67 Issue 6 Pages 538
    Published: 1992
    Released on J-STAGE: June 02, 2011
    JOURNAL FREE ACCESS
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  • Hiromu Momota, Yukihiro Tomita
    1992 Volume 67 Issue 6 Pages 539-549
    Published: June 25, 1992
    Released on J-STAGE: October 22, 2010
    JOURNAL FREE ACCESS
    The principle of D-3He fueled fusion which mitigates engineering problems attributed to 14 MeV neutrons is presented as well as the requirements needed to constitute an attractive D-3He fusion reactor. The intrinsic characteristics of a field-reversed configuration appears to meet the requirements. Potential and critical issues are discussed on the bases of a comprehensive D-3He fueled FRC reactor design “ARTEMIS”, which definitely offers the most attractive prospect of the energy development for the 21st century: It is inherently safe and environmentally acceptable in view of radioactivity and fuel resources. Further, the estimated cost of electricity is low compared to a light water reactor. An experimental research program needed to develop the D-3He fueled FRC fusion reactors is discussed.
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  • Dong Sheng Cai, Akira Aoyagi
    1992 Volume 67 Issue 6 Pages 550-553
    Published: June 25, 1992
    Released on J-STAGE: October 22, 2010
    JOURNAL FREE ACCESS
    The K-dV equation for ion acoustic wave is derived without using the reductive perturbation method or the multiple-time-scale perturbation method. The only assumptions adopted in deriving the K-dV equation from the continuity, momentum and the Poisson equation are that: (1) the ion speed is low; and (2) the charge separation in plasmas is weak.
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