Neutronic study of the 2-MW TRIGA MARK-II research reactor by the deterministic codes DRAGON5 & DONJON5

• Published in: Applied radiation and isotopes 2020-03, Vol.157, p.109026-109026, Article 109026
• Main Authors: El Yaakoubi, H., Boukhal, H., El Bardouni, T., Chakir, E., El Hajjaji, O., Chham, E., El Bakkari, B., Boulaich, Y., Azougagh, M.
• Format: Article
• Language: English
• Subjects: Control rods worth; DRAGON5 & DONJON5; Excess reactivity; Power peaking factor; TRIGA MARK-II
• ISSN: 0969-8043; 1872-9800
• DOI: 10.1016/j.apradiso.2019.109026

The main objective of this work is to perform a neutronic study of the 2 MW TRIGA MARK-II research reactor of the National Centre of Sciences, Energy and Nuclear Techniques (CNESTEN), Rabat, Morocco and then validate the results by comparing the experimental values and those published for an ordinary 2 MW TRIGA MARK II research reactor. The core diffusion code DONJON5 and the lattice code DRAGON5 were coupled to perform a full model of the TRIGA core and their consistency and accuracy were established by benchmarking the TRIGA experiments. In this study, the nuclear data libraries ENDF/B-VII.1 and JEFF3.1 based on 172 energy groups were used. The group constants of all the reactor components were generated using DRAGON5 code and the collision probability method. These group constants were used then in the DONJON5 core code to calculate the multiplication factor, core excess reactivity, total and integral control rods worth as well as power peaking factors. Good agreement found between the calculated and measured results. •Neutronic calculations of the TRIGA MARK II research reactor.•Validation of the deterministic transport code DRAGON5 and diffusion code DONJON5.•Calculation and analysis of control rod worth, excess reactivity as well as power peaking factors by deterministic codes.•The good consistency of the results ensures that a thermal-hydraulic analysis will be performed for TRIGA reacteor.•To rely on DRAGON5 and DONJON5 codes for TRIGA Mark-II calculations.