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首页> 美国政府科技报告 >Report on preliminary laboratory experiments investigating consequences of failure of front hydraulic fittings in K reactor geometry
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Report on preliminary laboratory experiments investigating consequences of failure of front hydraulic fittings in K reactor geometry

机译：报告初步实验室实验，研究前部液压配件在K反应器几何结构中失效的后果

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The purpose of this report is to present the results of a brief series of transient heat transfer experiments directed toward determining the possibility of damage to a K reactor should a front hydraulic connector fail to a tube containing I&E fuel elements. Nuclear heating of a train of 32 I&E slugs was simulated by electrically heating a rod in a K geometry process tube. Failure of a front fitting to such a tube was simulated by simultaneously and rapidly closing a valve in the water supply to the tue and opening a valve in a line which permitted discharge from the inlet of the tube through a front nozzle to atmosphere. Two to three seconds after the valve operation, a power reduction was initiated. The power reduction was in accord with an 800 inhour scram, except for two runs at 1,500 inhours. The reverse flow, rear header pressure and eight rod thermocouples, as well as other less important variables, were monitored. A test was continued until rod temperatures of 450 to 500 C were reached or until conditions of adequate cooling were established. With the exception of one run at 750 KW, all runs were with an initial tube power of 1,000 KW. The experimental program was terminated by failure of the test section.

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