Modeling Flow Characteristics of Reactor Sumps

by 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,


Serial Information: Journal of the Energy Division, 1982, Vol. 108, Issue 3, Pg. 169-184


Document Type: Journal Paper

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.

Subject Headings: Scale models | Submerged flow | Emergency management | Hydraulic models | Free flow | Accidents | Power plants | Hydro power

Services: Buy this book/Buy this article

 

Return to search