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O'Brien, M.H.; Merrill, B.J.; Ugaki, S.N.
EG and G Idaho, Inc., Idaho Falls, ID (USA)1988
EG and G Idaho, Inc., Idaho Falls, ID (USA)1988
AbstractAbstract
[en] Oxidation rates of four nuclear grade graphite products --- Union Carbide TS1792m Poco AFX-5Q, FMI 4D Weave C-C Composite, and Pfizer pyrolytic --- were measured from 800 to 1800 degree C for two air flow rates. With the resulting data, power balance modeling was used to predict the rates of graphite tile loss for the proposed Compact Ignition Tokamak (CIT) reactor under different accident scenarios. Experimental results show that above ∼1000 degree C the reaction rate is controlled by the oxygen supply. Below this temperature the reaction rate is controlled by chemical kinetics and oxygen supply. Calculated activation energies for these two kinetic regions were 18.8 and 47.5 kJ/mol, respectively. An accident scenario was proposed in which both a top and a bottom viewing port seal were broken while tile surface temperatures were still at 1100 degree C. Predictions based upon simple energy balance modeling indicate that a significant portion of the protective tiles on the CIT vacuum vessel could be oxidized, possibly releasing a significant amount of hazardous tritium oxide. Further analytical studies are proposed. 22 refs., 12 figs., 1 tab
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Sep 1988; 30 p; CONTRACT AC07-76ID01570; NTIS, PC A03/MF A01 as DE90013090; OSTI; INIS; US Govt. Printing Office Dep
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