
doi: 10.2172/10163347 , 10.2172/6503074
Following a hypothetical Loss of Coolant Accident (LOCA) the moderator level in the reactor tank would decrease. The current operating procedure with the new Type Q Septifoil is to maintain Septifoil cooling during a LOCA. With the Type Q Septifoil the coolant flows up the Septifoil to ports above and just below the Poison Plate where it is discharged into the reactor tank. The coolant would then spray from the top of the Septifoil, splashing onto the Universal Sleeve Housings (USH) which house the assemblies, and enhance the cooling of the assemblies. The goal of the experiments performed in the HTL under Task Plan 92-062-1 was to determine the flow rate down the outside of the USH as a function of Septifoil flow. Information on USH cooling is necessary in the calculation of Gamma Heating Power Limits for K Reactor. This task (92-062-1) parallels a similar task (90-074-1) which was performed to redesign the Septifoil (Type Q) and verify its performance. The facility that was used was the same test facility as that used by the previous task, namely Poison Plate Flow Test Rig. A relationship between the flow rate inside a Septifoil to the water collected by an USHmore » is presented. The test apparatus consisted of three Septifoils, each surrounded by six USHs. The geometry is prototypic of the reactor. Supplemental testing was performed after a preliminary investigation of the early results showed a drop in the USH collection flow rate near a Septifoil flow rate of about 7 GPM. The supplemental data supported the earlier data at low flow rate (<10 GPM) an expanded the range of data to 20 GPM by resolving nonprototypic issues.« less
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Data Analysis, Us Aec, Test, Loss Of Coolant, Sleeves, Production Reactors, Us Doe, K Reactor, Hydraulics, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Mechanics, Reactor Accidents, 220600, Engineering, Reactor Safety 220900, Information, Safety Engineering, Training, 220600 -- Nuclear Reactor Technology-- Research, Hydrogen Compounds, Special Production Reactors, Flow Rate, Data, Reactor Safety, 22 General Studies Of Nuclear Reactors, Research, Us Erda, Production, Water, Savannah River Plant, Test & Experimental Reactors, Reactors, Heat Transfer, Us Organizations 220900* -- Nuclear Reactor Technology-- Reactor Safety, 620, Numerical Data, Energy Transfer, Accidents, Experimental Data, Irradiation, Safety, Materials Testing Reactors, Oxygen Compounds, Heavy Water Moderated Reactors, Cooling, National Organizations
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