Dr. Md. Jahirul Haque Khan, BSc and MSc in Physics, MS in Nuclear Engineering at KAIST, South Korea (2005), PhD in Reactor Physics (2014), Jahangirnagar University, Bangladesh, is chief scientific officer and Head, Reactor Physics and Engineering Division (RPED) of INST, AERE, Bangladesh Atomic Energy Commission. His research interests are neutronics analysis of nuclear reactor, nuclear data processing and radiation protection and shield design analysis using various reactor engineering computer codes. 

 

The goal of this study is to analyze the neutronics and the kinetics parameters of the present core configuration of 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC) from the viewpoint of reactor safety and also to validate the calculated results of the neutronics and the kinetics safety parameters by benchmarking with the experimental, available safety analysis report (SAR) values and also earlier published MCNP results (numerically benchmark). This analysis was carried out effectively with the help of a comprehensive deterministic neutronics calculation code system SRAC2006 based on the Japanese Evaluated Nuclear Data Library JENDL-3.3 and the USA Evaluated Nuclear Data Library ENDF/B-VII.0. The collision probability method lattice transport code SRAC-PIJ for cell calculation and the 3-D diffusion code SRAC-CITATION for core calculation were employed to develop the model of the TRIGA core. The model represents in details all components (fuel and non-fuel) of the core and its immediate neighborhood with exactly no physical approximation. All fresh fuel and control elements as well as the vicinity of the core were precisely included in TRIGA model. Therefore, the results obtained from this analysis will be very essential to develop the neutronics data and reactor kinetics data newly based on the updated evaluated nuclear data libraries (JENDL-3.3 and ENDF/B-VII.0) from the view point of safety analysis for a wide spectrum of 3 MW TRIGA Mark-II reactor calculations. In addition, the results of this analysis can be used as the inputs for thermal-hydraulic calculations of the TRIGA fresh core in the steady state and the pulse mode operations.