Neutronic study of ELECTRA using reprocessed fuel and depleted uranium

Clarysson Alberto Mello da silva; Paola Machado de Almeida; Claubia Claubia Pereira

doi:10.15392/2319-0612.2024.2677

Authors

Clarysson Alberto Mello da silva Universidade Federal de Minas Gerais http://orcid.org/0000-0002-3082-644X
P. M. de Almeida Universidade Federal de Minas Gerais
Pereira C. Universidade Federal de Minas Gerais

DOI:

https://doi.org/10.15392/2319-0612.2024.2677

Keywords:

Small Modular Reactors, Lead Cooled Reactor, ELECTRA, MCNP6.2.0

Abstract

The present work simulates the European Lead Cooled Training Reactor (ELECTRA), focusing on studying the neutronic parameters of a small fast nuclear reactor. The goal is to evaluate the possibility of incinerating minor actinides and the potential for energy production from ²³⁸U. The simulations consider the following scenarios: depleted uranium mixed with the reprocessed fuel, and individual fuel rods containing only depleted uranium positioned at different locations within the reactor core. The results show that the use of reprocessed fuels could contribute to the reduction of minor actinides, while the use of depleted uranium reduces reactor criticality by acting as a neutron absorber. Most uranium nuclides do not undergo fission during burnup, which increases their isotopic concentration.

Downloads

Download data is not yet available.

Author Biography

Clarysson Alberto Mello da silva, Universidade Federal de Minas Gerais

Professor Adjunto da Universidade Federal de Minas Gerais (UFMG) onde desenvolve atividades de ensino e de pesquisa no Departamento de Engenharia Nuclear (DENU). Possui Doutorado (2009) e Mestrado (2005) em Ciências e Técnicas Nucleares pela UFMG, Especialização em Ensino de Física - Universidade Federal de Ouro Preto (UFOP, 2000) e Graduação em Matemática (Licenciatura Plena) - Faculdades Integradas Newton Paiva (FINP, 1996). Possui experiência na área de Engenharia Nuclear com ênfase em Tecnologia Nuclear, atuando em temas relacionados a simulação de sistemas nucleares, reatores avançados, ciclo do combustível, transmutação nuclear e reprocessamento do combustível queimado.

References

[1] IAEA. Technology roadmap for small modular reactor deployment. International Atomic Energy Agency, Vienna, Austria, 2021.

[2] SUN, X.Y., HAN, L.H., LI, X.X., HU, B. L., LUO, W., LIU, L. Transmutation of MAs and LLFPs with a lead-cooled fast reactor. Scientific Reports, v. 13, 1693, 2023.

[3] ADAMOV., E. Chapter 22 – New generation reactor technologies within the framework of Generation IV International Forum, Closed Nuclear Fuel Cycle with Fast Reactors. In: Academic Press, 2022, ISBN 9780323993081.

[4] SMITH, C. F., CINOTTI, L. Chapter 6 – Lead-cooled Fast Reactors (LFRs), Handbook of Generation IV Nuclear Reactors. In: Woodhead Publishing Series in Energy (Second Edition), Woodhead Publishing, 2023, ISBN 9780128205884.

[5] ALEMBERTI, A., TUCEK, K., M. Takahashi, OBARA, T., KONDO, M., MOISEEV, A., TOCHENY, L., SMITH, C., HWANG, I. S., WU, Y., JIN, M. Lead-Cooled Fast Reactor (LFR) System Safety Assessment. Generation IV International Forum, 2020.

[6] ALEMBERTI, A., FEOGHERI, M. L., HERMSMEYER, S., L. AMMIRABILE, L., SMIRNOV, V., TAKAHASHI, M., SMITH, C.F., WU, Y., HWANG, I. S. Lead-cooled Fast Reactor (LFR) Risk and Safety Assessment White Paper. Generation IV International Forum, 2014.

[7] JIN, X., ZHANG, Z., SUN, Y., LIU, M., XIAO, Y., GUO, H., JIANG, X., CHEN, L., GU, H. Preliminary safety comparison of lead-cooled fast reactors with advanced fuels in unprotected transients. Nuclear Engineering and Design, v. 411, 112419, 2023.

[8] AGBEVANU, K. T.; DEBRAH, S. K., ARTHUR, E. M., SHITSI, E. Liquid metal cooled fast reactor thermal hydraulic research development: A review. Heliyon, v. 9 (6), e16580, 2023.

[9] WALLENIUS, J., SUVDANTSETSEG, E., FOKAU, A. ELECTRA: European Lead-Cooled Training Reactor. Nuclear Technology, v. 177(3), p. 303–313, 2012.

[10] SUVDANTSETSEG, E. Neutronics and Transient Analysis of a Small Fast Reactor Cooled with Natural Circulation of Lead. KHT Royal Institute of Technology, Doctoral Thesis, Stockholm (Sweden), 2014.

[11] COTA, S.; PEREIRA, C. Neutronic Evaluation of the Non-Proliferating Reprocessed Nuclear Fuels in Pressurized Water Reactors. Annals of Nuclear Energy, Brazil, v. 24, p. 829-834, 1997.

[12] MIRGUIRDITCHIAN, M., CHAREYRE, L., HERES, X., HILL, C., BARON, P., MASSON, M. Ganex: adaptation of the Diamex-Sanex process for the group actinide separation. In: Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems, 2007, Boise, Idaho, 2007.

[13] C. A. M. SILVA; N G. P. L. OLIVEIRA; I. K. UMEZU; C PEREIRA; A L. COSTA. Neutronic Evaluation of a Small Lead-Cooled Nuclear Reactor as an Actinides Burner. Nuclear Engineering and Design, Brazil, v. 417, n. 112796, 2024.

[14] WALLENIUS, J., SUVDANTSETSEG, E., BORTOT, S., PUKARI, М., JOLKKONEN, M., CLAISSE, A., OLSSON, P., EJENSTAM, J., SZAKALOS, P. ELECTRA: A Lead Cooled Reactor for Training and Education. Series: Nuclear Reactor Constants, Sweden, UDC 621.039.55, n. 4, 2015.

[15] DUDERSTADT, J. J., HAMILTON, L. J. Reactor Analysis. In: WILEY, J. 1st edition, 1976, ISBN 978-0471223634.