Prediction of the in-core power and the average core temperature using dose-rate measurements in the Syrian Miniature Neutron Source Reactor

被引：0
|
作者：
I. Khamis
M. H. Jamal
机构：
[1] Department of Nuclear Engineering,
[2] Atomic Energy Commission,undefined
[3] Department of Nuclear Engineering,undefined
[4] Atomic Energy Commission,undefined
来源：
Journal of Radioanalytical and Nuclear Chemistry | 2006年 / 269卷
关键词：
Reactor Power; Neutron Flux; Research Reactor; Thermal Neutron Flux; Reactor Operation;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
The measurement of the dose-rate on the top-surface of the Miniature Neutron Source Reactor (MNSR) has been used to monitor the in-core reactor power and estimate the average core temperature. An experimental correlation for the prediction of both reactor power level and average core-coolant temperature as functions of dose-rate measurement have been obtained. An alternative method for both neutron flux monitoring and average core temperature using dose-rate measurement has been suggested. Comparing the results with the calibrated reactor power, reasonable agreement between predicted and real data measurement has been found. Despite of this agreement, the measurement of dose-rate on top of the MNSR surface as an additional mean for the prediction of in-core power or average core temperature should be considered carefully.
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页码：81 / 85
页数：4
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