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Thermal neutron flux measurement using self-powered neutron detector (SPND) at out-core locations of TRIGA PUSPATI Reactor (RTP)

机译:使用自动中子探测器(SPND)在Triga Puspati反应器(RTP)外核心位置的热中子磁通测量

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The thermal neutron flux measurement has been conducted at the out-core location using self-powered neutron detectors (SPNDs). This work represents the first attempt to study SPNDs as neutron flux sensor for developing the fault detection system (FDS) focusing on neutron flux parameters. The study was conducted to test the reliability of the SPND's signal by measuring the neutron flux through the interaction between neutrons and emitter materials of the SPNDs. Three SPNDs were used to measure the flux at four different radial locations which located at the fission chamber cylinder, 10cm above graphite reflector, between graphite reflector and tank liner and fuel rack. The measurements were conducted at 750 kW reactor power. The outputs from SPNDs were collected through data acquisition system and were corrected to obtain the actual neutron flux due to delayed responses from SPNDs. The measurements showed that thermal neutron flux between fission chamber location near to the tank liner and fuel rack were between 5.18x10~(11) nv to 8.45x10~9 nv. The average thermal neutron flux showed a good agreement with those from previous studies that has been made using simulation at the same core configuration at the nearest irradiation facilities with detector locations.
机译:使用自动中子探测器(SPND)在外核位置进行了热中子磁通测量。这项工作代表了研究SPNDS作为中子磁通传感器的首次尝试,用于开发专注于中子磁通参数的故障检测系统(FDS)。通过通过测量通过SPND的中子和发射器材料之间的相互作用来测试SPND信号的可靠性来测试SPND信号的可靠性。使用三个SPND来测量位于裂变室圆筒的四个不同径向位置的磁通,在石墨反射器上方10cm,石墨反射器和罐衬里和燃料架之间。测量以750 kW反应器功率进行。通过数据采集系统收集来自SPND的输出,并且校正以获得由于SPND的延迟响应而获得的实际中子磁通量。测量结果表明,靠近罐衬里和燃料架附近的裂变室位置之间的热中子磁通为5.18x10〜(11)NV至8.45×10〜9 nV。平均热中子通量与先前研究的综合吻合吻合良好,这些研究已经在最近的芯片设施中使用仿真设施在具有探测器位置的相同核心配置中进行的。

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