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Gorman, D.J.
Atomic Energy of Canada Ltd., Ottawa, Ontario1972
Atomic Energy of Canada Ltd., Ottawa, Ontario1972
AbstractAbstract
No abstract available
Original Title
Suitable for fog-cooled reactors
Primary Subject
Source
7 Nov 1972; 9 p; CA PATENT DOCUMENT 914146; Available from Commissioner of Patents, Ottawa; Filed 13 Aug 1970. Priority USA 18 Sept 1969 (858,946). 6 claims, 2 drawings. Available from Commissioner of Patents, Ottawa.
Record Type
Patent
Country of publication
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INIS VolumeINIS Volume
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Pettigrew, M.J.; Gorman, D.J.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.1977
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.1977
AbstractAbstract
[en] Vibration experiments were done on small tube bundles of triangular and square lattice configurations in both liquid and two-phase (air-water) cross-flow. The effects of flow velocity, simulated steam quality, lattice orientation, tube location and tube frequency were explored. Tube response to random flow turbulence excitation and fluidelastic instability were observed in both liquid and two-phase cross-flow. Fluidelastic instability criteria and random forcing function characterizations are derived from this work. This information may be used in the vibration analysis of shell-and-tube heat exchanger components. (author)
Primary Subject
Source
Jun 1977; 20 p; International symposium on vibration problems in industry; Keswick, England; 10 - 12 Apr 1973; 17 refs.
Record Type
Report
Literature Type
Conference
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Cheng, S.C.; Gorman, D.J.
Ottawa Univ., Ontario (Canada)1975
Ottawa Univ., Ontario (Canada)1975
AbstractAbstract
No abstract available
Primary Subject
Source
1975; vp; 5. Canadian congress of applied mechanics; Fredericton, N.B., Canada; 26 May 1975; Published in ''Proceedings of the Fifth Canadian Congress of Applied Mechanics, Fredericton, May 26-30, 1975''.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Pettigrew, M.J.; Gorman, D.J.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.1973
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.1973
AbstractAbstract
No abstract available
Primary Subject
Secondary Subject
Source
May 1973; 12 p; International symposium on vibration problems in industry; Keswick, UK; 10 Apr 1973; 10 refs.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Gorman, D.J.; Mueller, J.W.
Bureau International des Poids et Mesures, 92 - Sevres (France)1972
Bureau International des Poids et Mesures, 92 - Sevres (France)1972
AbstractAbstract
No abstract available
Primary Subject
Source
1972; 12 p
Record Type
Report
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Country of publication
Reference NumberReference Number
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INIS IssueINIS Issue
AbstractAbstract
[en] An extensive series of experimental vibration tests has been conducted on tube bundles of contemporary interest in a large water tunnel. The main objective of these tests has been to develop a design criterion to limit vibration amplitudes. It has been found that the main excitation mechanisms are turbulence, some vortex shedding, and hydroelastic instability. The results of these tests are correlated and presented. It is found that the most serious excitation mechanism is hydroelastic instability. Criteria are advanced for establishing upper velocity limits based on the experimental findings. The vortex shedding mechanism is found to only be a problem for tubes in the inlet region of some bundles. Strouhal numbers associated with observed resonances are tabulated and discussed. Tube response to random turbulence has been studied for numerous bundles but is found to be of secondary significance
Primary Subject
Record Type
Journal Article
Journal
Nuclear Science and Engineering; v. 61(3); p. 324-336
Country of publication
Reference NumberReference Number
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INIS IssueINIS Issue
Cheng, S.C.; Gorman, D.J.; Kulkarni, K.
American Society of Mechanical Engineers, New York1975
American Society of Mechanical Engineers, New York1975
AbstractAbstract
[en] A thermodynamic analysis for surge tank pressure transients during multiple surges in a nuclear reactor is presented. A sinusoidal type of level changes has been assumed. (U.S.)
Original Title
PHWR
Primary Subject
Source
1975; 5 p; Joint fluids engineering and lubrication conference; Minneapolis, Minnesota, USA; 5 May 1975; ASME, New York, NY $3.00.
Record Type
Report
Literature Type
Conference
Report Number
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Reference NumberReference Number
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AbstractAbstract
[en] It has been demonstrated in a convincing fashion by the author that liquid turbulence, some vortex shedding at bundle inlet tubes, and hydroelastic instability are the main causes of vibration in bundles of current interest. Hydroelastic instability thresholds can be fairly well predicted. There are many ways in which real prototype heat exchangers deviate from laboratory tube bundles. In the work reported here, numerous experimental tests have been conducted to determine the effect on permissible design velocity limits of these deviations. All tests have been conducted in a horizontal water tunnel containing tube bundles of contemporary interest. Tests have been conducted to determine whether or not open tube lanes will serve to trigger hydroelastic instabilities at abnormally low velocities. It is found that, in fact, they do not. Further tests were conducted to investigate the effect of varying the clearance between the bundle and the tunnel wall. The effects on vibration of various shapes of baffle plates located along the tunnel wall was investigated. Preferred baffle plate designs have been established. Mixed bundles of tubes of different frequencies were tested. The effects of locating baffles in the bundle inlet region were studied experimentally. It will be appreciated that all of the results reported are immediately applicable in the design of modern heat exchangers and steam generators. (Auth.)
Primary Subject
Source
Jaeger, T.A.; Boley, B.A. (eds.); International Association for Structural Mechanics in Reactor Technology; Commission of the European Communities, Brussels (Belgium); v. F p. F6/2 1-13; ISBN 0 444 85062 7; ; 1977; v. F p. F6/2 1-13; North-Holland; Amsterdam, Netherlands; 4. international conference on structural mechanics in reactor technology; San Francisco, USA; 15 - 19 Aug 1977
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The sources, production and releases of tritium in gaseous and liquid effluents from CANDU stations as well as applicable regulatory and derived emission standards are discussed. To assess the environmental impact of these releases, Ontario Hydro has been carrying out an environmental monitoring programme at all nuclear generating sites since 1971. The programme monitors critical and potentially important pathways and consists of monitoring tritium in air, precipitation, milk, drinking water and vegetation. Tritium releases from stations are of the order of 0.1% of the derived release limits leading to doses to individuals in the vicinity of the stations of about 1 mrem/a-1. The environmental impact from an expanded CANDU programme is discussed. The effects on the Great Lakes basin are of particular importance since it is expected that the bulk of Ontario Hydro's future nuclear sites will be located along the shores of the Great Lakes. The implication of the recently promulgated International Joint Commission water quality objective is examined. (author)
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); Nuclear Energy Agency, 75 - Paris (France); Proceedings series; p. 623-633; ISBN 92-0-020079-6; ; 1979; p. 623-633; IAEA; Vienna; International symposium on the behaviour of tritium in the environment; San Francisco, CA, USA; 16 - 20 Oct 1978; IAEA-SM--232/49
Record Type
Book
Literature Type
Conference; Numerical Data
Country of publication
BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, DATA, DATA FORMS, HEAVY WATER MODERATED REACTORS, HYDROGEN ISOTOPES, INFORMATION, ISOTOPES, LAKES, LIGHT NUCLEI, MONITORING, NUCLEI, NUMERICAL DATA, ODD-EVEN NUCLEI, POWER REACTORS, PRESSURE TUBE REACTORS, RADIOISOTOPES, REACTORS, SURFACE WATERS, THERMAL REACTORS, YEARS LIVING RADIOISOTOPES
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Real prototype heat exchangers deviate from laboratory tube bundles. In the work reported here, numerous experimental tests have been conducted to determine the effect on permissible design velocity limits of these deviations. All tests have been conducted in a horizontal water tunnel containing tube bundles of contemporary interest. Tests have been conducted to determine whether or not open tube lanes will serve to trigger hydroelastic instabilities at abnormally low velocities. It is found that, in fact, they do not. Further tests were conducted to investigate the effect of varying the clearance between the bundle and the tunnel wall. Results indicate that a clearance of not less than half a tube diameter prevents local vibration problems. The effect on vibration of various shapes of baffle plates located along the tunnel wall was investigated. Preferred baffle plate designs have been established. Clearances of one tube bundle gap width between baffle plates and adjacent tubes are shown to be desirable. Mixed bundles of tubes of different frequencies were tested. Vibration test demonstrated that this is not the way to improve heat exchanger design. The effects of locating baffles in the bundle inlet region were tested. It was found that the distance between the plate and the bundle was not of critical importance. Other geometric effects were studied. The first hydroelastic tests on clamped-simply supported tube bundles have now been completed. The new data are found to fit remarkably well on the previously used stability diagram. At the time of writting, the effect of clearances at the tube end supports is being studied. With controlled clearances in the laboratory, it is found that a knocking action occurs at these supports even at extremely low velocities. The implication of these tests, as they pertain to multi-span heat exchangers is discussed
Primary Subject
Source
v. F; 1977; F 6/2, 13 p; 4. International conference on structural mechanics in reactor technology; San Francisco, Calif., USA; 15 - 19 Aug 1977
Record Type
Miscellaneous
Literature Type
Conference
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