OXIDATION OF UOS AT 400 TO 1000 CELCIUS IN AIR AND ITS RELEVANCE TO FISSION PRODUCT RELEASE. PDF Download
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Languages : en
Pages : 50
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Languages : en
Pages : 50
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Author: D. R. Mccracken
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Category :
Languages : en
Pages : 0
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Category :
Languages : en
Pages :
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Author: Atomic Energy of Canada Limited
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Category :
Languages : en
Pages : 78
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Author: D. R. Mccracken
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Category :
Languages : en
Pages : 0
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Two mechanistically different regimes have been observed during the oxidation of uo2 in air: at temperatures greater than or equal to 800 degrees c, u3o8 forms large crystals which propagate in a front through the underlying u4o9/uo2; at temperatures less than 700 degrees c, one grain of uo2 ultimately gives one or more grains of u3o8. previous experiments (1) indicated that in this latter temperature zone, releases of fission products are low and probably originate from inventory at grain boundaries. the experiments described here at 950 degrees c using high burnup fuel (445, 465 mw.h/kg u) confirm earlier results obtained with low burnup fuel (2) at 920 degrees c: in this temperature zone, 100 percent of the volatile fission products are released when u3o8 is formed by oxidation of uo2 in air. within experimental error, oxidation rates and corresponding release rates are independent of burnup, so that data on oxidation rates obtained using unirradiated pellets can be used to estimate release rates of fission products during oxidation of irradiated fuel. iodine, in the form of i2, is released from the uranium matrix as readily as the noble gases, but subsequently adsorbs in steel pipework thus reducing its volatility in a real system. cs release was also observed. it lagged behind the iodine, ruling out csi as the volatile species.
Author: Mohammad Mehdi Sadeghi
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Category :
Languages : en
Pages : 228
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Author: D. R. Mccracken
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Category :
Languages : en
Pages : 0
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Fission product release and redistribution was studied during the exposure of uo2 in a zirconium furnace tube to steam and air at temperatures up to 910 degrees c. the fuel fragments had been exposed to less than or equal to 3.11 x 10 sup(18) n/cm sup(2) (0.3 mw.h/kg) at less than or equal to 70 degrees c in the self-serve facility of nrx. under these conditions no diffusion to grain boundaries should have occurred, and fission products should stay randomly scattered throughout the matrix. releases were small, less than or equal to 1.4 percent with only xenon and iodine being significant. the fuel oxidation occurred predominantly at less than or equal to 700 degrees c. at higher temperatures oxidation of the zirconium occurred and protected the fuel from significant high temperature oxidation. the results illustrate that fission gases distributed in the fuel matrix are not released during simple crystallographic re-arrangement. release occurs only when an atomic site or gas bubble is intersected by a crack or dislocation. significantly higher release should be expected under conditions where grain growth occurs. selective traps for fission products performed well and will be further investigated in future studies.
Author: H. C. Stoner
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Category : Fission products
Languages : en
Pages :
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Category : Nuclear engineering
Languages : en
Pages : 312
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Author:
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Category : Air
Languages : en
Pages : 1184
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