Measurement and simulation of thermal neutron flux distribution in the RTP core

International Nuclear Science, Technology and Engineering Conference 2017

原子能学

Rabir, Mohamad Hairie B.^1 ; Jalal Bayar, Abi Muttaqin B.^1 ; Hamzah, Na'Im Syauqi B.^1 ; Mustafa, Muhammad Khairul Ariff B.^1 ; Abdul Karim, Julia Bt.^1 ; Mohamed Zin, Muhammad Rawi B.^1 ; Ismail, Yahya B.^1 ; Hussain, Mohd Huzair B.^1 ; Mat Husin, Mat Zin B.^1 ; Md Dan, Roslan B.^1 ; Ismail, Ahmad Razali B.^1 ; Husain, Nurfazila Bt.^1 ; Abdul Jalil Khan, Zareen Khan B.^1 ; Mohd Yakin, Shaiful Rizaide B.^1 ; Saad, Mohamad Fauzi B.^1 ; Masood, Zarina Bt.^1

Reactor Technology Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, Selangor Kajang

43000, Malaysia^1

关键词: Flux calculations;    Measurement and simulation;    Monte Carlo codes;    Neutron flux distributions;    Over-estimation;    Self-powered neutron detectors;    Thermal fluxes;    Thermal-neutron flux;   

Others  :  https://iopscience.iop.org/article/10.1088/1757-899X/298/1/012029/pdf
DOI  :  10.1088/1757-899X/298/1/012029

来源: IOP

【 摘 要 】

The in-core thermal neutron flux distribution was determined using measurement and simulation methods for the Malaysian's PUSPATI TRIGA Reactor (RTP). In this work, online thermal neutron flux measurement using Self Powered Neutron Detector (SPND) has been performed to verify and validate the computational methods for neutron flux calculation in RTP calculations. The experimental results were used as a validation to the calculations performed with Monte Carlo code MCNP. The detail in-core neutron flux distributions were estimated using MCNP mesh tally method. The neutron flux mapping obtained revealed the heterogeneous configuration of the core. Based on the measurement and simulation, the thermal flux profile peaked at the centre of the core and gradually decreased towards the outer side of the core. The results show a good agreement (relatively) between calculation and measurement where both show the same radial thermal flux profile inside the core: MCNP model over estimation with maximum discrepancy around 20% higher compared to SPND measurement. As our model also predicts well the neutron flux distribution in the core it can be used for the characterization of the full core, that is neutron flux and spectra calculation, dose rate calculations, reaction rate calculations, etc.