Monte Carlo Simulations for a Preliminary Design of TRIGA IPR-R1 PGAA Facility  

作　　者：Bruno Teixeira Guerra Alexandre Soares Leal Claubia Pereira Maria Angela de Barros Correia Menezes 

机构地区：[1]DEN (Departamento de Engenharia Nuclear), UFMG (Universidade Federal de Minas Gerais), Av. Antonio Carlos 6627, Campus Pampulha, CEP 31270 901, Belo Horizonte, Minas Gerais, Brazil [2]CDTN (Nuclear Technology Development Center), CNEN (Brazilian Commission for Nuclear Energy), Av. Antonio Carlos 6627, Campus UFMG, CEP 31270 901, Belo Horizonte, Minas Gerais, Brazil

出　　处：《Journal of Chemistry and Chemical Engineering》2016年第6期256-270,共15页化学与化工（英文版）

摘　　要：In this paper, the evaluation of a preliminary design of a PGAA （prompt gamma activation analysis） facility based on Monte Carlo simulations is presented and discussed. The implementation of the PGAA method at the CDTN （nuclear technology development centre） would increase the applications of the TRIGA reactor. The preliminary design is based on a quasi vertical hollow cylinder （called neutron extractor） in the reactor pool to extract the neutron flux. This study evaluates the neutron flux in the upper position of the cylinder in the suggested position of the samples to be analyzed by the PGAA. The calculations of the radioactive capture reaction rates and of the detection limits for some isotopes were performed. Through all these calculations, the feasibility of the application of the PGAA method at the IPR-R1 installations was evaluated. According to the obtained results, it can be concluded that is possible to apply the PGAA method at the IPR-R1 reactor, even with its design restrictions.

关 键 词：PGAA facility neutron activation analysis TRIGA IPR-R1 PGAA NAA. 

分 类 号：O572.212[理学—粒子物理与原子核物理] TU311.2[理学—物理]