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Neutronics analysis of TRIGA Mark II research reactor

This article presents clean core criticality calculations and control rod worth calculations for TRIGA (Training, Research, Isotope production-General Atomics) Mark II research reactor benchmark cores using Winfrith Improved Multi-group Scheme-D/4 (WIMS-D/4) and Program for Reactor In-core Analysis using Diffusion Equation (PRIDE) codes. Cores 133 and 134 were analyzed in 2-D (r, q) and 3-D (r, q, z), using WIMS-D/4 and PRIDE codes. | Nuclear Engineering and Technology 50 2018 35 42 Contents lists available at ScienceDirect Nuclear Engineering and Technology journal homepage www.elsevier.com locate net Original Article Neutronics analysis of TRIGA Mark II research reactor Haseebur Rehman a Siraj-ul-Islam Ahmad b a Department of Nuclear Engineering PIEAS Nilore Islamabad Pakistan b Research in Modeling and Simulation RIMS Group Department of Physics CIIT Park Road Islamabad Pakistan Check for updates ARTICLE INFO ABSTRACT Article history Received 9 March 2017 Received in revised form 27 September 2017 Accepted 16 November 2017 Available online 8 December 2017 Keywords Control rod worth Criticality calculations ENDF B-Vi endf b-vii JEF-2.2 Jeff-3.1 JENDL-3.2 Program for Reactor In-core Analysis using Diffusion Equation TRIGA reactor Winfrith Improved Multi-group Scheme-D 4 This article presents clean core criticality calculations and control rod worth calculations for TRIGA Training Research Isotope production-General Atomics Mark II research reactor benchmark cores using Winfrith Improved Multi-group Scheme-D 4 WIMS-D 4 and Program for Reactor In-core Analysis using Diffusion Equation PRIDE codes. Cores 133 and 134 were analyzed in 2-D r 9 and 3-D r 9 z using WIMS-D 4 and PRIDE codes. Moreover the influence of cross-section data was also studied using various libraries based on Evaluated Nuclear Data File ENDF B-VI.8 and VII.0 Joint Evaluated Fission and Fusion File JEFF-3.1 Japanese Evaluated Nuclear Data Library JENDL-3.2 and Joint Evaluated File JEF-2.2 nuclear data. The simulation results showed that the multiplication factor calculated for all these data libraries is within 1 of the experimental results. The reactivity worth of the control rods of core 134 was also calculated with different homogenization approaches. A comparison was made with experimental and reported Monte Carlo results and it was found that using proper homogenization of absorber regions and surrounding fuel regions the .