Actran: a code for depletion calculations in PWR cores aiming the production of minor actinide for using in ads

• Autor(a) principal: Santos, Rubens Souza dos
• Data de Publicação: 2018
• Outros Autores: Instituto de Engenharia Nuclear
• Tipo de documento: Artigo de conferência
• Idioma: por
• Título da fonte: Repositório Institucional do IEN
• Texto Completo: http://carpedien.ien.gov.br:8080/handle/ien/2476
• topic: Ciclo do combustível nuclear; Teoria de difusão multigrupo; Equações de depleção; Métodos numéricos; ADS

Despite of the renewed willing to accept nuclear power as a mean of mitigate the climate changing, to deal with the long lived waste still cause some concerning in relation to maintain in safety condition, during so many years. A technological solution to overcome this leg of time is to use a facility that burn these waste, besides to generate electricity. This is the idea built in the accelerator driven systems (ADS). This technology is being though to use some minor actinides (MAs) as fuel. This work presents a program to assess actinide concentrations, aiming a fertile-free fuel to be used in the future ADS technology. For that, use was made of a numerical code to solve the steady-state multigroup diffusion equation 3D to calculate the neutron fluxes, coupled it with a new code to solve, also numerically, depletion equations, named ACTRAN code. This paper shows the simulation of a PWR core during the residence time of the nuclear fuel, for three years, and after, for almost four hundred years, to assess the MAs production. The results show some insight in the best management to get a minimum amount of some MAs to use in the future generations of ADS.