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Ohkawa, I.; Futaki, M.; Yamanouchi, H.
Transactions of the 10th international conference on structural mechanics in reactor technology1989
Transactions of the 10th international conference on structural mechanics in reactor technology1989
AbstractAbstract
[en] The nuclear power reactor buildings have been constructed on the hard rock ground formed in or before the Tertiary in Japan. This is mainly because the nuclear reactor building is much heavier than the common buildings and requires a large bearing capacity of the underlying soil deposit, and additionally the excessive deformation in soil deposit might cause damage in reactor building and subsequently cause the malfunction of the internal important facilities. Another reason is that the Quaternary soil deposit is not fully known with respect to its dynamic property. The gravel, and the sandy gravel, the representative soils of the Quaternary, have been believed to be suitable soil deposits to support the foundation of a common building, although the soils have rarely been investigated so closely on their physical properties quantitatively. In this paper, the dynamic deformability, i.e., the shear stress-strain relationship of the Quaternary diluvial soil deposit is examined through the earthquake ground motion measurement using accelerometers, pore-pressure meters, the specific devices developed in this research work. The objective soil deposit in this research is the sandy gravel of the diluvial and the alluvial
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Source
Hadjian, A.H. (Bechtel Power Corp., Los Angeles, CA (USA)); Seismic response analysis and design; 967 p; ISBN 0-9623306-0-4; ; 1989; p. 267-272; American Association for Structural Mechanics in Reactor Technology; Los Angeles, CA (USA); 10. international conference on Structural Mechanics in Reactor Technology (SMIRT); Anaheim, CA (USA); 14-18 Aug 1989; CONF-890855--; American Association for Structural Mechanics in Reactor Technology, P.O. Box 60860, Los Angeles, CA 90060 (USA)
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Book
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Conference
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Ueda, K.; Yamanouchi, H.
Proceedings of the 28. Arctic and Marine Oilspill Program (AMOP) Technical Seminar2005
Proceedings of the 28. Arctic and Marine Oilspill Program (AMOP) Technical Seminar2005
AbstractAbstract
[en] This paper presented a solution to the problem of recovering spilled oil from a sunken ship, particularly when the oil viscosity is high. In such cases, the pipe friction resistance becomes large and oil transfer becomes difficult. In this study, the pipe pressure drop from the pipe entrance to the exit was measured, and the friction factor was obtained. The flow rate in the pipe was then calculated. The oil flow rate of the oil injected into the water was compared with cases where only the oil flowed and with an annular water injection method (AWI). The method of transporting viscous oil by injecting it in a water current proved to be a simple and effective method for reducing the friction coefficient of the pipe. In oil laminar flow, the friction drag was reduced by inserting the oil into water with a simple T joint, thereby increasing the amount of oil transfer. 3 refs., 1 tab., 7 figs
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Source
Environment Canada, Ottawa, ON (Canada). Emergencies Science and Technology Div; Environment Canada, Ottawa, ON (Canada). Environmental Technology Centre. Funding organisation: Environment Canada, Ottawa, ON (Canada). Emergencies Science and Technology Div; Environment Canada, Ottawa, ON (Canada). Environmental Technology Centre; Environment Canada, Ottawa, ON (Canada). Environmental Protection Service; 1134 p; 2005; p. 437-446; 28. Arctic and Marine Oilspill Program (AMOP) Technical Seminar; Calgary, AB (Canada); 7-9 Jun 2005; Available from Environment Canada, Emergencies Science and Technology Division, Environmental Technology Centre, 335 River Road, Ottawa, Ontario, K1A 0H3; v.1
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AbstractAbstract
No abstract available
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Journal Article
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Progress Report
Journal
Mitsubishi Juko Giho; v. 7(3); p. 267-274
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AbstractAbstract
No abstract available
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Meeting of the American Nuclear Society; Washington, District of Columbia, USA; 27 Oct 1974; See CONF-741017-- Published in summary form only.
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Journal Article
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Conference
Journal
Trans. Amer. Nucl. Soc; v. 19 p. 291-292
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Yamanouchi, H.; Ohkawa, I.; Chiba, O.; Tohdo, M.; Kaneko, O.
Structural mechanics in reactor technology1987
Structural mechanics in reactor technology1987
AbstractAbstract
[en] The nuclear power plant reactor buildings are to be directly supported on a hard soil as a rule in Japan. In case of determining the input motions in order to design those buildings, the amplifications of the hard soil deposits are examined by the total stress analysis in general. However, when the supporting hard soil is replaced with the slightly softer medium such as sandy or gravelly soil, the existence of pore water, in other words, the contribution of the pore water pressure to the total stress cannot be ignored even in a practical sense. In this paper the authors defined an analytical model considering the effective stress-strain relation. In the analyses, the response in the vertical direction is used to evaluate the confining pressure, at first. In the next step, the process of the generation and dissipation of the pore water pressure, is taken into account, together with the effect of the confining pressure. They applied these procedures for the response computations of the horizontally layered soil deposits
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Source
Wittman, F.H; p. 343-348; ISBN 90-6191-771-9; ; 1987; p. 343-348; A.A. Balkema Publishers; Accord, MA (USA); 9. SMIRT: international conference on structural mechanics in reactor technology; Lausanne (Switzerland); 17-21 Aug 1987
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Book
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Conference
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AbstractAbstract
No abstract available
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Meeting of the American Nuclear Society; Washington, District of Columbia, USA; 27 Oct 1974; See CONF-741017-- Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Trans. Amer. Nucl. Soc; v. 19 p. 291
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] In order to recover spilled oil, it is necessary to be able to handle it within wide ranges of viscosity. To test oil properties, a series of tests were carried out to determine surface tension, and viscosity of oil as well as that of emulsified oil. The effects of temperature and relative content, both of which affect recovery, were also investigated. Highly viscous oil did not respond well to pumping. It was recovered with the aid of a net belt which allowed waves as well as water to flow through it while retaining the heavily viscous oil. Low viscosity oil layers had to be thickened at the recovery point to facilitate efficient pumping. 3 refs., 6 figs
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Source
Environment Canada, Ottawa, ON (Canada). Environmental Protection Service; 919 p; 1999; p. 773-780; Environment Canada; Ottawa, On (Canada); 22. Arctic and marine oil spill technical seminar; Calgary (Canada); 2-4 Jun 1999; Available from the Emergencies Science Division, Environment Canada, 3439 River Road, Ottawa, ON, Canada, K1A 0H3. Phone: (613) 998-9622. Fax: (613) 991-9485. Internet address: www.etcentre.org/conferences/index.html or through interlibrary loan from the CANMET Information Centre, 555 Booth St., Ottawa, ON, K1A 0G1, tel.: (613) 995-4132 or FAX: (613) 995-8730
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Miscellaneous
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Conference
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Yamanouchi, H.; Sato, K.; Higashiura, A.
Transactions of the 10th international conference on structural mechanics in reactor technology1989
Transactions of the 10th international conference on structural mechanics in reactor technology1989
AbstractAbstract
[en] In order to obtain the rational safety margins of the reactor building structure, experiments on scale-model specimens of reactor building structures conducted mainly in Japan are investigated to recognize the performance up to limit state. The absorbed energy is used as a measure of the limit state performance. The amount of absorbed energy is then compared to seismic input energy estimated with a simple energy input theory in order to incorporate the comparison in implications for seismic safety margins
Primary Subject
Source
Hadjian, A.H. (Bechtel Power Corp., Los Angeles, CA (USA)); Seismic response analysis and design; 967 p; ISBN 0-9623306-0-4; ; 1989; p. 515-520; American Association for Structural Mechanics in Reactor Technology; Los Angeles, CA (USA); 10. international conference on Structural Mechanics in Reactor Technology (SMIRT); Anaheim, CA (USA); 14-18 Aug 1989; CONF-890855--; American Association for Structural Mechanics in Reactor Technology, P.O. Box 60860, Los Angeles, CA 90060 (USA)
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Book
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Conference
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AbstractAbstract
[en] A 66-year-old MS patient who suffered respiratory arrest followed by complete remission is reported. Magnetic resonance imaging (MRI) revealed a medullary lesion. Clinicoradiological relationships are discussed. (orig.)
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Journal Article
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Kato, H.; Kitahara, T.; Yamanouchi, H.
Heat and fluid flow in water reactor safety. Conference sponsored by the Thermodynamics and Fluid Mechanics Group of the Institution of Mechanical Engineers, Manchester, 13-15 September 19771977
Heat and fluid flow in water reactor safety. Conference sponsored by the Thermodynamics and Fluid Mechanics Group of the Institution of Mechanical Engineers, Manchester, 13-15 September 19771977
AbstractAbstract
[en] The safety evaluation of an inlet tube break for the pressure tube reactor, FUGEN is described. The investigation was conducted by using the computer code SENHOR and the experimental results obtained at the Oarai Engineering Center, PNC. It was found that, for a smaller rupture at the inlet tube with a small leakage (<= 10 kg/s), sufficient core flow is expected even in the ruptured channel and the minimum critical heat flux ratio is expected to remain above 1.0 under full power operating condition. A postulated inlet tube break accident with large leakage (>10 kg/s) is also evaluated in comparison with the experiment. (author)
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Source
Institution of Mechanical Engineers, London (UK); IMechE Conference Publications 1977; no. 8; p. 125-130; ISBN 0 85298 379 4; ; 1977; p. 125-130; Mechanical Engineering Pub. for the Institution of Mechanical Engineers; London; Conference on heat and fluid flow in water reactor safety; Manchester, UK; 13 - 15 Sep 1977
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Book
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Conference
Country of publication
ACCIDENTS, COMPUTER CODES, FAILURES, FLUID FLOW, HEAT FLUX, HEAVY WATER MODERATED REACTORS, HWLWR TYPE REACTORS, MATHEMATICAL MODELS, NATURAL URANIUM REACTORS, PLUTONIUM REACTORS, POWER REACTORS, PRESSURE TUBE REACTORS, REACTOR ACCIDENTS, REACTOR PROTECTION SYSTEMS, REACTORS, THERMAL REACTORS, TUBES, WATER COOLED REACTORS
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