摘要
利用反应堆互功率谱密度(CPSD)测试系统对300~#池式研究堆的瞬发中子衰减常数α进行实验研究。堆芯采用低富集度U燃料装载,燃料组件有一定燃耗。测试系统以PCI-6143高速同步数据采集卡(DAQ)为测试硬件,以Labview8.5程序为开发软件;利用紧靠堆芯对称布置的2路γ补偿电离室探测器获得中子在堆内的连续电流信号,该信号输入到测试系统后,再应用数据采集和数据处理分析程序得到互谱密度,最后用非线性最小二乘法拟合得到瞬发中子衰减常数α为(83.5±0.6)s^(-1),结果与实际运行的情况相符合,表明本次带燃耗的瞬发中子衰减常数α测量是成功的。
The prompt neutron decay parameter α for 300# research reactor is experimentally studied by the reactor cross power spectral density (CPSD) measurement system. The reactor core is loaded with the used low enriched uranium with a certain burnup. The measurement system uses PCI-6143 high-speed synchronization DAQ and Labview8.5 program as the measurement hardware and development software, respectively. The continuous current signals of neutron in the reactor are acquired by the gamma compensation ionization chambers which are symmetrically positioned in the reactor core. The cross power spectral density, for the two channel signals, is computed using the application program of data acquirement and data process analysis. Finally, using the non-linear least squares method, the prompt neutron decay parameter α is fitted, i.e. α=(83.5±0.6)s^-1. The result accords to the real operation process, which shows that the measurement of the prompt neutron decay parameter α is successful.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2010年第4期12-15,共4页
Nuclear Power Engineering