GIOVANNI LARANJO DE STEFANI
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Artigo IPEN-doc 28091 The AP-Th 1000 an advanced concept to use MOX of thorium in a closed fuel cycle2019 - STEFANI, GIOVANNI L. de; MAIORINO, JOSE R.This work presents a study for the firsts 4 cycles of recharge of the reactor AP-Th1000, a version of the reactor AP1000 using mixed uranium and thorium oxides as fuel, which the feasibility studies had been already demonstrated in previous study for a first cycle. The AP-Th 1000 study is a proposal to start the thorium fuel cycle using the most common reactor technology in the nuclear industry, the Pressurized Water Reactors (PWR). A preliminary closed cycle study is carried out for the first 4 cycles where the production of 233U are evaluated. In cycles 2, 3 and 4, new assemblies with a fuel of the remaining uranium from the previous cycle are used instead of assemblies removed from the core, thus being a mixture of different uranium’s (232U, 233U, 234U, 235U, 236U and 238U) , where the additional fissile material inserted into the fuel to ensure the 18-month operation of the reactor comes from uranium oxides enriched at 20 w / o.. The results demonstrate the viability of the proposal and again using closed fuel cycle.Artigo IPEN-doc 24019 Feasibility to convert an advanced PWR from UO2 to a mixed (U,Th)O2 core2017 - STEFANI, GIOVANNI L. de; MAIORINO, JOSE R.; MOREIRA, JOAO M. de L.; SANTOS, THIAGO A. dos; ROSSI, PEDRO C.R.This work presents the neutronics and thermal hydraulics feasibility to convert the UO2 core of the Westinghouse AP1000 in a (U-Th)O2 core, rather than the traditional uranium dioxide, for the purpose of reducing long-lived actinides, especially plutonium, and generates a stock pile of 233U, which could in the future be used in advanced fuel cycles, in a more sustainable process and taking advantage of the large stock of thorium available on the planet and especially in Brazil. The reactor chosen as reference was the AP1000, which is considered to be one of the most reliable and modern reactor of the current Generation III, and its similarity to the reactors already consolidated and used in Brazil for electric power generation. The results show the feasibility and potentiality of the concept, without the necessity of changes in the core of the AP1000, and even with advantages over this. The neutron calculations were made by the SERPENT code. The results provided a maximum linear power density lower than the AP1000, favoring safety. In addition, the delayed neutron fraction and the reactivity coefficients proved to be adequate to ensure the safety of the concept. The results show that a production of about 260 Kg of 233U per cycle is possible, with a minimum production of fissile plutonium that favors the use of the concept in U-Th cycles.