STUDIES OF FAST REACTOR FUEL ELEMENT BEHAVIOR UNDER TRANSIENT HEATING TO FAILURE. II. INPILE EXPERIMENTS ON UO2 SAMPLES IN THE ABSENCE OF COOLANT.
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Published: 1965
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Published: 1965
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DOWNLOAD EBOOKAuthor: C. E Dickerman
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Published: 1964
Total Pages: 52
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DOWNLOAD EBOOKThe in-pile experimental survey reported here is one undertaken on uranium dioxide fuel samples as an extension of previous tests in the Transient Reactor Test Facility (TREAT) on metallic, fast-reactor fuel samples. Oxide test specimens were pseudo-EBR-II elements that were clad with EBR-II cladding thickness, of EBR-II fuel length, and thermally bonded to cladding with inert gas (rather than sodium). Samples were exposed to transient power bursts of the order of 0.5-sec. duration, in the absence of coolant, with production of heating rates up to the order of 4000 degrees C/sec. Radial temperature profiles in the fuel during power bursts were estimated to be comparatively uniform. Cladding temperature lagged behind the fuel temperature, thermal equilibrium between fuel and clad being reached about 2 sec. after the peak of the power pulse. Sample cooling was predominantly by thermal radiation.
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Published: 1970
Total Pages: 368
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DOWNLOAD EBOOKAuthor: R. R. Stewart
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Published: 1969
Total Pages: 30
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Published: 1965-07
Total Pages: 1004
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DOWNLOAD EBOOKAuthor: Argonne National Laboratory. Reactor Engineering Division
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Published: 1964-07
Total Pages: 212
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Published: 1965-07
Total Pages: 760
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DOWNLOAD EBOOKAuthor: U.S. Atomic Energy Commission. Division of Technical Information
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Total Pages: 976
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