Neutronic study of ELECTRA using reprocessed fuel and depleted uranium
- 1. Departamento de Engenharia Nuclear, UFMG (Brazil)
Description
The present work aims to develop a neutronic study of a small-scale lead-cooled nuclear system. The data of ELECTRA (European Lead Cooled Training Reactor) were used for the simulations, considering its similarities to a Micro Reactor. This reactor has been developed by the Royal Institute of Technology together with Uppsala University and Chalmers University of Technology, in Sweden. It is a low-power fast reactor (0.5MWth), created with the purpose of demonstrating technology and conducting research. In addition to having inherent system safety, it also enables the use of reprocessed fuels, such as (Pu,Zr)N. This paper examines the use of reprocessed fuel and depleted uranium in the ELECTRA reactor, in order to evaluate its primary neutronic parameters. The MCNP6 (Monte Carlo N-Particle, version 6) was used to simulate the neutronic behavior of ELECTRA considering two scenarios: depleted uranium diluted in reprocessed fuel; and depleted uranium located in specific fuel rods within the reactor core. The first stage evaluates different concentrations of depleted uranium diluted in the reprocessed fuel. The second phase stage examines the use of fuel rods with depleted uranium positioned at different location in ELECTRA core. (author)
Additional details
Publishing Information
- Publisher
- ABEN
- Imprint Place
- Rio de Janeiro, RJ (Brazil)
- ISBN
- 978-65-594-1256-3
- Imprint Title
- Proceedings of the INAC 2024: international nuclear atlantic conference. Nuclear Energy: assuring energy, health and food
- Imprint Pagination
- [1918 p.]
- Journal Page Range
- 4 p.
Conference
- Title
- 11. international nuclear atlantic conference; 23. meeting on nuclear reactor physics and thermal hydraulics - ENFIR; 16. meeting on nuclear applications - ENAN; 8. meeting on nuclear industry - ENIN; ExpoINAC exhibition; 10. Junior poster technical sessions
- Acronym
- INAC 2024
- Dates
- 6-10 May 2024
- Place
- Rio de Janeiro, RJ (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 56007471
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DEPLETED URANIUM; FUEL REPROCESSING PLANTS; LEAD COOLED REACTORS; MONTE CARLO METHOD; NEUTRONS; NUCLEAR FUELS; RESEARCH REACTORS; URANIUM
- Descriptors DEC
- ACTINIDES; BARYONS; CALCULATION METHODS; ELEMENTARY PARTICLES; ELEMENTS; ENERGY SOURCES; FERMIONS; FUELS; HADRONS; LIQUID METAL COOLED REACTORS; MATERIALS; METALS; NUCLEAR FACILITIES; NUCLEONS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; URANIUM
Optional Information
- Notes
- Presentation in Jr Poster format - JR01: https://inac2024.aben.org.br/files/final/23840.pdf