科技报告详细信息
Fuel Temperature Coefficient of Reactivity. | |
Loewe, W. E. | |
Technical Information Center Oak Ridge Tennessee | |
关键词: Control elements; Natural uranium; Savannah river plant; Oscillations; Production reactors; | |
RP-ID : DE2001784244 | |
学科分类:工程和技术(综合) | |
美国|英语 | |
来源: National Technical Reports Library | |
【 摘 要 】
A method for measuring the fuel temperature coefficient of reactivity in a heterogeneous nuclear reactor is presented. The method, which is used during normal operation, requires that calibrated control rods be oscillated in a special way at a high reactor power level. The value of the fuel temperature coefficient of reactivity is found from the measured flux responses to these oscillations. Application of the method in a Savannah River reactor charged with natural uranium is discussed.
【 预 览 】
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DE2001784244.pdf | 1054KB | download |