Research Article
Nov 1982
Modeling Flow Characteristics of Reactor Sumps
Publication: Journal of the Energy Division
Volume 108, Issue 3
Abstract
After a postulated loss of coolant accident in a nuclear powerplant, heated water from the core is removed through the emergency reactor building floor sump, cooled, and reinjected into the core or the containment building via the spray system. Reduced scale models of reactor sumps are demonstrated to be an efficient means to assure the hydraulic performance of the emergency core cooling system is adequate for long term operation. Similitude criteria for model operation are described, considering the phenomena of interest such as free surface and submerged vortices, swirling flow in the pump suction lines, and energy losses in the flow path. Typical model scale ratios, construction techniques, instrumentation, and operating procedures are described. Test results from several typical recent studies are used to illustrate design features which are desirable and those that are undesirable.
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Information
Published In
Journal of the Energy Division
Volume 108 • Issue 3 • November 1982
Pages: 169 - 184
Copyright
© 1982 American Society of Civil Engineers.
History
Published in print: Nov 1982
Published online: Feb 11, 2021
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Authors
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James B. Nystrom
Lead Research Engr. and Instr.; of Mech. Engrg.; Alden Research Lab., Worcester Polytechnic Inst., Holden, Mass. 01520
Mahadevan Padmanabhan
Lead Research Engr. and Asst. Prof. of Mech. Engrg.; Alden Research Lab., Worcester Polytechnic Inst., Holden, Mass. 01520
George E. Hecker, M.ASCE
Dir. and Assoc. Prof. of Civ. Engrg., Alden Research Lab., Worcester Polytechnic Inst., Holden, Mass. 01520
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Terms of Use: ASCE Library Cards are for individual, personal use only. Reselling, republishing, or forwarding the materials to libraries or reading rooms is prohibited.