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

被引：2
|
作者：
Ali, Nur Syazwani Mohd [1 ]
Hamzah, Khaidzir [1 ]
Idris, Faridah Mohamad [2 ]
Rabir, Mohamad Hairie [2 ]
机构：
[1] Univ Teknol Malaysia, Dept Energy Engn, Fac Chem & Energy Engn, Johor Baharu 81310, Johor, Malaysia
[2] Agensi Nuklear Malaysia, Kajang 43000, Selangor, Malaysia
来源：
INTERNATIONAL NUCLEAR SCIENCE, TECHNOLOGY AND ENGINEERING CONFERENCE 2017 (INUSTEC2017) | 2018年 / 298卷
关键词：
D O I：
10.1088/1757-899X/298/1/012027
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
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.
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页数：7
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