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

International Nuclear Science, Technology and Engineering Conference 2017

原子能学

Mohd Ali, Nur Syazwani^1 ; Hamzah, Khaidzir^1 ; Idris, Faridah Mohamad^2 ; Rabir, Mohamad Hairie^2

Department of Energy Engineering, Faculty of Chemical and Energy Engineering, Universiti Teknologi Malaysia, Johor, Johor Bahru

81310, Malaysia^1

Malaysian Nuclear Agency, Bangi Selangor Kajang

43000, Malaysia^2

关键词: Core configuration;    Data acquisition system;    Delayed response;    Emitter materials;    Fault detection systems;    Irradiation facilities;    Self-powered neutron detectors;    Thermal-neutron flux;   

Others  :  https://iopscience.iop.org/article/10.1088/1757-899X/298/1/012027/pdf
DOI  :  10.1088/1757-899X/298/1/012027

来源: IOP

【 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 5.18 × 1011nv to 8.45 × 109nv. 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.