Estratégias de gerenciamento de reatividade para um reator nuclear de água pressurizada integral

Mazaira, Leorlen Y. Rojas; Betancourt, Mariana Cecilia; Hernández, Carlos Rafael García; García, Jesús Alberto Rosales; Lira, Carlos Alberto Brayner de Oliveira

doi:10.18605/2175-7275/cereus.v12n4p26-45

Cited by 3 publications

(1 citation statement)

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“…However, controlling the large excess reactivity of the core using only burnable absorbers and control rods is another major challenge for core design. Several studies about mPower fuel cycle design and reactivity management strategies have been published [7]- [10]. The core was designed to achieve a fuel cycle length of 4-year in a one-batch core design.…”

Section: Core Size and Configurationmentioning

confidence: 99%

Computational model for thermohydraulic analysis of an integral pressurized water reactor with mixed oxide fuel (Th, Pu)O2

Betancourt

Santos²,

Mazaira³

et al. 2022

Braz. J. Rad. Sci.

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The use of advanced generation III+ and IV nuclear reactors, and their applications, has become important, seen as a means capable of contributing to the global transition to more sustainable, affordable and reliable energy systems. This technology, which could be integrated into future carbon-free electric power generation systems with high proportions of different renewable energy sources, includes Small Modular Reactors (SMR). There are about 100 different proposed projects of Generation III+ and IV, of which about 50 are SMR concepts, in various stages of development and of different types of technologies. Other important issues for achieving the long-term sustainability of nuclear energy are the proper use of its fuel sources and the improvement of nuclear waste management. Therefore, fuels based on a mixture of oxides have been used successfully in several countries. In addition, the incorporation of thorium-based fuel is a current challenge for the new designs of advanced reactors. The present paper focuses on the analysis of a small modular integral pressurized water reactor (iPWR) with Thorium-Uranium Oxide (Th-U MOX) mixtures. A thermohydraulic model is developed using the Ansys CFX program, which allows the calculation of the temperature distribution in the section where the highest power is produced within the SMR IPWR core (critical section). The temperature distributions in the fuel, clad and coolant were calculated with the objective of verifying that they were within the safety limits.

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Section: Core Size and Configurationmentioning

confidence: 99%