Neutronic Evaluation of Using a Thorium Sulfate Solution in an Aqueous Homogeneous Reactor

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چکیده

Radioisotope 99 Mo is one of the most essential radioisotopes in nuclear medicine. Its production an Aqueous Homogeneous Reactor (AHR) could be potentially advantageous compared to traditional technology, based on target irradiation a heterogeneous reactor. An AHR conceptual design using low-enriched uranium for has been studied depth. So far, possibility replacing with non-uranium fuel, specifically mixture 232 Th and 233 U, not evaluated design. Therefore, studies conducted this article aim evaluate neutronic behavior thorium sulfate solution. Here, Th- U composition guarantee ten years operation without refueling, conversion ratio, medical isotopes levels, reactor kinetic parameters were evaluated, computational code MCNP6. It was obtained that 14 % enrichment guarantees refueling. The ratio calculated at 0.14. resulted 24.4 higher fuel than fuel.

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ژورنال

عنوان ژورنال: Atom Indonesia

سال: 2022

ISSN: ['0126-1568', '2356-5322']

DOI: https://doi.org/10.17146/aij.2022.1188