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- W127869828 abstract "The results of as analytical and experimental program to obtain knowledge concerning thermal design unknowns for pressurized water reactors are described. Experimental techniques used are described. The outof-pile tests simulated nuclear heating by using elecrically heated test sections. The in-pile experiments were performed with specially instrumented and loaded fuel elements installed in a reactor to measure appropriate thermal and hydraulic conditions. Results on the following subjects are included: experiments on the surface effects of nucleate boiling; pressure drop tests; heat transfer burnout tests; transient loss-of-coolantflow experiments with an operating reactor; and reactor performance during operation at limiting thermal and hydraulic conditions. (M.H.R.)" @default.
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- W127869828 date "1958-10-31" @default.
- W127869828 modified "2023-09-26" @default.
- W127869828 title "THERMAL AND HYDRAULIC EXPERIMENTS FOR PRESSURIZED WATER REACTORS" @default.
- W127869828 hasPublicationYear "1958" @default.
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