Journal of High Pressure Institute of Japan
Online ISSN : 1347-9598
Print ISSN : 0387-0154
ISSN-L : 0387-0154
Search
Advanced search
OR
Browse
Search
Volume 27, Issue 3
Displaying 1-5 of 5 articles from this issue
Show all abstracts
    • |<
    • <
    • 1
    • >
    • >|
  • Thermal Conductivity Measurement under High Pressure by Transient Hot Wire Method
    JUN-ICHI SUSAKI, KI-ITI HORAI
    1989 Volume 27 Issue 3 Pages 122-129
    Published: May 25, 1989
    Released on J-STAGE: August 05, 2010
    DOIhttps://doi.org/10.11181/hpi1972.27.122
    JOURNAL FREE ACCESS
    Download PDF (828K)
  • Weldability of 9 Cr-1 Mo-Nb-V Steel
    Ryoichi KUME, Kenji MATSUI, Hisaki OKABAYASHI
    1989 Volume 27 Issue 3 Pages 130-139
    Published: May 25, 1989
    Released on J-STAGE: August 05, 2010
    DOIhttps://doi.org/10.11181/hpi1972.27.130
    JOURNAL FREE ACCESS
    Show abstractHide abstract
    The weldability of 9Cr-1Mo-Nb-V steel was studied using casting, forging and heavy section pipe.
    The obtained results are as follows;
    (1) Minimum preheating temperature to prevent cold cracking in y groove restraint specimen is about 200°C, which is lower than the values estimated from the chemistry of 9Cr-1 Mo-Nb-V steel used and ordinary 2.25Cr-1Mo steel.
    (2) The degrease in susceptibility of the cold cracking of weldments made with electrode of matching composition can be interpreted by cosidering relief of thermal shrinkage caused by martensitic transformation of weld metals which, then, lowers degree of residual stress in restraint condition.
    (3) The susceptibility to hot cracking is the same or less than that of Type 304 stainless steel and far less than that of Type 316 or Type 347 stainless steel.
    (4) Long time heating embrittlement phenomenon was not observed for 9Cr-1 Mo-Nb-V welded joints under the condition of 600°C for 5000 hours.
    (5) Newly developed 9Cr-1 Mo-Nb-V casting shows sufficient weldability for welding production.
    View full abstract
    Download PDF (953K)
  • Eddy-Current Testing of Nuclear Fuel Cladding Tubes Using Tilted Encircling Coil System
    Ist Report, Basic Characteristics of Defect Signals
    Renzhong YIN, Kazuyoshi SEKINE, Hisaji SHIMIZU, Kazushige TSUKUI, Megu ...
    1989 Volume 27 Issue 3 Pages 140-149
    Published: May 25, 1989
    Released on J-STAGE: August 05, 2010
    DOIhttps://doi.org/10.11181/hpi1972.27.140
    JOURNAL FREE ACCESS
    Show abstractHide abstract
    The eddy current testing method with external encircling-coils has been widely used as a standard technique for inspection of defects in irradiated zircaloy cladding tubes. In this inspection, the systematic procedure to reliably characterize defects is required.
    This paper describes the newly developed external tilted encircling-coil system, in which the coil axis is inclined by an angle α to the sample tube axis, for reliable determination of the sort, location and size of defects. As the results of experimental work concerning some kinds of artificial defects in zircaloy cladding tubes using newly designed tilted coil system, an adaptable general-procedure for characterization of defects has been proposed. Furthermore, it has been confirmed that in the case of smaller tilt angles of coil, the signal-to noise ratio for defect response in this coil system is approximately equal to that of ordinary encircling coil system.
    View full abstract
    Download PDF (988K)
  • Implosion Strength of Liner Tube on Double Wall Pipe
    Shigetomo MATSUI, Takao YOSHIKAWA, Katsuyuki KAKEI, Koji KUBOYAMA, Tos ...
    1989 Volume 27 Issue 3 Pages 152-160
    Published: May 25, 1989
    Released on J-STAGE: August 05, 2010
    DOIhttps://doi.org/10.11181/hpi1972.27.152
    JOURNAL FREE ACCESS
    Show abstractHide abstract
    Mechanically fitted double wall pipe is developed as low cost anti-corrosion pipe. As a liner tube of the double wall pipe is not metallurgically bonded with outer pipe, it is feared that implosion of the liner tube may be caused by interface gas pressure resulted from leakage of working pressure through unexpected crack or damage when the working pressure is suddenly evacuated.
    This paper describes the evaluation of implosion strength of the liner tube of a tightly fitted double wall pipe.
    View full abstract
    Download PDF (2525K)
  • A Study on the Creep Damage Analysis for Oil Reforming Reactor
    Tetsuyuki HIROE, Katsuzo SUDO, Mitsuo TANI, Shigetoshi SHINDO
    1989 Volume 27 Issue 3 Pages 161-169
    Published: May 25, 1989
    Released on J-STAGE: August 05, 2010
    DOIhttps://doi.org/10.11181/hpi1972.27.161
    JOURNAL FREE ACCESS
    Show abstractHide abstract
    The present paper describes a life prediction based on inelastic analysis for nozzle and skirt junctions of oil reforming reactor.
    Creep tests for weld material elements and notched weld joint specimens of 11/4Cr-1/2Mo steel were carried out at 525°C and the results represented that reproduced HAZ specimens with a long-term rupture time had a remarkably reduced ductility.
    The comparison between test results and life prediction for notched specimens showed that the analytical evaluation of creep damage using stress-or strain-base criteria could be put into practical use.
    The elastic-plastic-creep behavior and the damage accumulation were analysed on nozzle and skirt junctions of actual reforming reactors such as platformer (11/4Cr-1/2Mo) and Continuous Catalyst Reformer (21/4Cr-1Mo).
    As the results, the influence of stress relaxation behavior on the life prediction and the importance of appropriate definition of the effective stress for damage calculation became clear, and the simplified estimation of the relaxed stress were examined.
    View full abstract
    Download PDF (2556K)
    • |<
    • <
    • 1
    • >
    • >|
feedback
 Top