Medical Radioisotope Production in a Power-Flattened ADS Fuelled with Uranium and Plutonium Dioxides

Bakır, Gizem; Selçuklu, Saltuk Buğra; Yapıcı, Hüseyin

doi:10.1155/2016/5302176

Cited by 2 publications

(2 citation statements)

References 23 publications

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“…One example of ADS is the MYRRHA project [9]. ADS can also be used for the production of neutron-rich radioisotopes as a result of their high neutron flux characteristics, while producing power at the same time [10]. All these qualities together can increase the value of ADS despite their added complexity with respect to critical reactors.…”

Section: Accelerator-driven Subcritical Reactorsmentioning

confidence: 99%

Simulating the Production of Medical Radioisotopes in a Fast Thorium-Cycle ADS with SERPENT

Nath-M¹

2021

WJNST

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Radiopharmaceuticals are used in nuclear medicine for diagnostic or therapeutic acts. The short decay half-lives of medical radioisotopes, especially those used for diagnostics, imply that they should be produced continuously and transported as quickly as possible to the medical units where they are used. Neutron-rich medical radioisotopes are generally produced in research reactors, like technetium-99m, lutetium-177, holmium-166 and iodine-131. On the other hand, proton-rich radioisotopes are produced via reactions with charged particles from accelerators like fluorine-18, gallium-67, iodine-123 and thallium-201. Beside this, innovative nuclear reactors are advocated as solutions to the issues of nuclear waste production and proliferation threats. Fast neutron, thorium-cycle and accelerator-driven subcritical (ADS) reactors are some of the most promising of them, proposed as safer fuel breeders and "waste burners". This article examines the use of a fast thorium-cycle ADS with liquid lead-bismuth eutectic coolant for the production of molybdenum-99/technetium-99m and lutetium-177. Burnup simulation has been made with the Monte-Carlo (MC) code SERPENT. It is demonstrated that MC codes can advantageously be used to determine the optimal irradiation time for a given radioisotope in a realistic reactor core. It is also shown that fast thorium-cycle ADS is an economical option for the production of medical radioisotopes.

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Section: Accelerator-driven Subcritical Reactorsmentioning

confidence: 99%

Simulating the Production of Medical Radioisotopes in a Fast Thorium-Cycle ADS with SERPENT

Nath-M¹

2021

WJNST

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“…Peak-to-average fission power density ratio of the blanket is decreased to almost 1.1. Bakır et al [30] have investigated the medical radioisotope production performance of a power-flattened ADS fuelled with UO 2 and PuO 2 . Their results show that a good quasi-uniform power density is achieved and good neutronic performance in terms of energy production, radioisotope production, and the transmutation of spent fuel is also achieved.…”

Section: Introductionmentioning

confidence: 99%

Time-Dependent Neutronic Analysis of a Power-Flattened Gas Cooled Accelerator Driven System Fuelled with Thorium, Uranium, Plutonium, and Curium Dioxides TRISO Particles

Bakır

Genç

Yapıcı

2016

Science and Technology of Nuclear Installations

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This study presents the power flattening and time-dependent neutronic analysis of a conceptual helium gas cooled Accelerator Driven System (ADS) loaded with TRISO (tristructural-isotropic) fuel particles. Target material is lead-bismuth eutectic (LBE). ThO2, UO2, PuO2, and CmO2TRISO particles are used as fuel. PuO2and CmO2fuels are extracted from PWR-MOX spent fuel. Subcritical core is radially divided into 10 equidistant subzones in order to flatten the power produced in the core. Tens of thousands of these TRISO fuel particles are embedded in the carbon matrix fuel pebbles as five different cases. The high-energy Monte Carlo code MCNPX 2.7 with the LA150 library is used for the neutronic calculations. Time-dependent burnup calculations are carried out for thermal fission power (Pth) of 1000 MW using the BURN card. The energy gain of the ADS is in the range of 99.98–148.64 at the beginning of a cycle. Furthermore, the peak-to-average fission power density ratio is obtained between 1.021 and 1.029 at the beginning of the cycle. These ratios show a good quasi-uniform power density for each case. Furthermore, up to 155.1 g233U and 103.6 g239Pu per day can be produced. The considered system has a high neutronic capability in terms of energy multiplication, fissile breeding, and spent fuel transmutation with thorium utilization.

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Medical Radioisotope Production in a Power-Flattened ADS Fuelled with Uranium and Plutonium Dioxides

Cited by 2 publications

References 23 publications

Simulating the Production of Medical Radioisotopes in a Fast Thorium-Cycle ADS with SERPENT

Simulating the Production of Medical Radioisotopes in a Fast Thorium-Cycle ADS with SERPENT

Time-Dependent Neutronic Analysis of a Power-Flattened Gas Cooled Accelerator Driven System Fuelled with Thorium, Uranium, Plutonium, and Curium Dioxides TRISO Particles

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