Optimizing irradiation conditions for natural molybdenum in WWR-K reactor
2
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
The production of the radioisotope molybdenum-99 in the WWR-K research reactor is achieved through the activation method 98Mo(n,γ)99Mo, utilizing a target of natural molybdenum trioxide irradiated under standard conditions (thermal neutron spectra and water environment). Under such conditions, the maximum specific activity of molybdenum-99 reaches (2.3 ± 0.3) Ci/g Mo after 7 d of irradiation. However, the escalating demand for molybdenum-99 and the need to reduce its production cost, necessitates urgent and increased productivity. This study aims to optimize the irradiation conditions for molybdenum powder in the WWR-K reactor to increase the specific activity of molybdenum-99. For this purpose, we evaluated various irradiation capsule designs comprised various neutron moderator materials and thicknesses. Through extensive modeling calculations, we obtained an optimal capsule design that increases the specific activity of molybdenum-99 to 3.31 Ci per 1 g of Mo.
Abstract
The production of the radioisotope molybdenum-99 in the WWR-K research reactor is achieved through the activation method 98Mo(n,γ)99Mo, utilizing a target of natural molybdenum trioxide irradiated under standard conditions (thermal neutron spectra and water environment). Under such conditions, the maximum specific activity of molybdenum-99 reaches (2.3 ± 0.3) Ci/g Mo after 7 d of irradiation. However, the escalating demand for molybdenum-99 and the need to reduce its production cost, necessitates urgent and increased productivity. This study aims to optimize the irradiation conditions for molybdenum powder in the WWR-K reactor to increase the specific activity of molybdenum-99. For this purpose, we evaluated various irradiation capsule designs comprised various neutron moderator materials and thicknesses. Through extensive modeling calculations, we obtained an optimal capsule design that increases the specific activity of molybdenum-99 to 3.31 Ci per 1 g of Mo.
참고문헌 (17)
- "Report on molybdenum-99 production for nuclear medicine 2010–2020" (2008)[URL]
- Feasibility of producing molybdenum-99 on a small scale using fission of low enriched uranium or neutron activation of natural molybdenum, in: Technical Reports Series, "IAEA", International Atomic Energy Agency, ~, pp.No. 478 (2015)
- "The IAEA research reactor database" (2024)[URL]
- Production Technologies for Molybdenum-99 and Technetium-99m, "IAEA", International Atomic Energy Agency, ~ (1999)
- M. Blaauw, "Estimation of 99Mo production rates from natural molybdenum in research reactors", J. Radioanal. Nucl. Chem, 311, pp.409~418 (2017)[DOI]
- Non-HEU production technologies for molybdenum-99 and technetium-99m, "IAEA", International Atomic Energy Agency, ~, pp.IAEA Nuclear Energy Series No. NF-T-5.4 (2013)
- A. I. Ryabchikov, "Obtaining molybdenum-99 in the IRT-T research reactor using resonance neutrons", Nucl. Instrum. Methods Phys. Res., Sect. A B (2004)
- S. Abrashkin, "Epithermal neutron self-shielding in the reactor (n, γ) production of 99Mo", Int. J. Appl. Radiat. Isot, 36(5), pp.385~388 (1985)[DOI]
- A. A. Shaimerdenov, "The 50th anniversary of the WWR-K research reactor", Phys. At. Nucl, 81, pp.1408~1411 (2018)[DOI]
- D. S. Sairanbayev, "Time history of performance parameters of WWR-K reactor during gradual replacement of the water reflector by a beryllium one", Russ. Phys. J, 63(12), pp.2165~2177 (2021)[DOI]
- A. Shaimerdenov, "WWR-K reactor LEU core design optimization for improving the experimental characteristics", Ann. Nucl. Energy, 195, pp.110174~ (2024)[DOI]
- Technology for Production of Portable TC-99M Gel Generators Using Neutron Activated Natural Molybdenum Almaty, Republic of Kazakhstan, "E. Chakrova", International Atomic Energy Agency, ~ (2015)
- G. E. Kodina, "Methods of Obtaining Radiopharmaceuticals and Radionuclide Generators for Nuclear Medicine: a Textbook for Universities" (2014), Publishing House of MEI
- A. A. Shaimerdenov, "Computational analysis of a neutron trap in the center of the WWR-K reactor core for irradiation tests of large-sized objects", Eurasian journal of physics and functional materials, 6(1), pp.38~46 (2022)[DOI]
- Production of Molybdenum-99 Using Neutron Capture Methods, "James J. Toth", ~ (2011)
- MCNP Version 6.2 Release Notes, "Christopher John Werner", ~ (2018)
- D. A. Brown, "ENDF", B-VII.1 nuclear Data for science and technology: cross sections, covariances, fission product yields and decay Data, 2011, pp.112, 2887~2996