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PreprintarXiv licencearXiv

Core reduction for increasing neutron flux and radioisotope production in the IEA-R1 research reactor

Abstract

This work aims to present and analyze a new reactor core configuration for the IEA-R1 reactor core with the objective of enhancing its neutron irradiation capabilities. The reactor was modeled using the KENO-VI module from the SCALE Code System, provided by ORNL. Results have shown that implementing a near-cylindrical configuration with 20 fuel elements in the IEA-R1 core could substantially increase neutron flux, particularly in the center irradiation positions such as the EIBe (Beryllium Irradiated Element). After comparing various configurations, we conducted a brief analysis of the proposed core configuration's potential to produce 177Lu, resulting in a 34% increase in the specific activity of 177Lu considering a fuel power cycle around 21 days.

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BibTeX
@misc{viggiano2026core,
  title = {{Core reduction for increasing neutron flux and radioisotope production in the IEA-R1 research reactor}},
  author = {Felipe Viggiano and Giovanni Laranjo de Stefani and Frederico A. Genezini and João M. L. Moreira and Caio J. C. M. Cunha},
  howpublished = {arXiv},
  year = {2026},
  month = nov,
  doi = {10.48550/arxiv.2611.05409},
  eprint = {2611.05409},
  archivePrefix = {arXiv},
  url = {https://arxiv.org/abs/2611.05409},
}
RIS
TY  - UNPB
TI  - Core reduction for increasing neutron flux and radioisotope production in the IEA-R1 research reactor
AU  - Felipe Viggiano
AU  - Giovanni Laranjo de Stefani
AU  - Frederico A. Genezini
AU  - João M. L. Moreira
AU  - Caio J. C. M. Cunha
PY  - 2026
DA  - 2026/11/01
PB  - arXiv
DO  - 10.48550/arxiv.2611.05409
UR  - https://arxiv.org/abs/2611.05409
AB  - This work aims to present and analyze a new reactor core configuration for the IEA-R1 reactor core with the objective of enhancing its neutron irradiation capabilities. The reactor was modeled using the KENO-VI module from the SCALE Code System, provided by ORNL. Results have shown that implementing a near-cylindrical configuration with 20 fuel elements in the IEA-R1 core could substantially increase neutron flux, particularly in the center irradiation positions such as the EIBe (Beryllium Irradiated Element). After comparing various configurations, we conducted a brief analysis of the proposed core configuration's potential to produce 177Lu, resulting in a 34% increase in the specific activity of 177Lu considering a fuel power cycle around 21 days.
ER  -