Investigation of 99Mo potential production via UO2SO4 liquid target irradiation in a 5 MW nuclear research reactor
Author:
Gholamzadeh Zohreh1, Mirvakili Seyed Mohammad1, Davari Amin1, Alizadeh Mosoumeh1, Joz-Vaziri Atieh1
Affiliation:
1. Reactor Research School, Nuclear Science and Technology Research Institute, Tehran, Iran (Islamic Republic of)
Abstract
Abstract
The activation method for 99Mo production in comparison to fissionable target irradiation in research reactors is less preferable. Therefore, 99Mo yield using UO2SO4 samples was theoretically investigated. Computational results revealed admirable potential of the liquid samples for 99Mo production. Low-concentrated uranyl sulphate samples could easily be handled by the irradiation box. The sample geometry optimization improves thermal hydraulic conditions and production yield. The optimized geometry including only 0.12 g 235U produced 57Ci99Mo at end-of-irradiation (EOI) with a temperature peak of 72°C during the irradiation.
Publisher
Walter de Gruyter GmbH
Subject
Waste Management and Disposal,Condensed Matter Physics,Safety, Risk, Reliability and Quality,Instrumentation,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference29 articles.
1. 1. Rao, A., Kumar Sharma, A., Kumar, P., Charyulu, M. M., Tomar, B. S., & Rama Kumar, K. L. (2014). Studies on separation and purification of fission 99Mo from neutron activated uranium aluminum alloy. J. Appl. Radiat. Isot., 89, 186–191. DOI: 10.1016/j.apradiso.2014.02.013. 2. 2. Muenze, R., Juergen Beyer, G., Ross, R., Wagner, G., Novotny, D., Franke, E., Jehangir, M., Pervez, S., & Mushtaq, A. (2013). The fission-based 99Mo production process ROMOL-99 and its application to PINSTECH Islamabad. Sci. Technol. Nucl. Install., 2013, Article ID 932546, 9 pp. http://dx.doi.org/10.1155/2013/932546. 3. 3. Ali, K. L., Ahmad Khan, A., Mushtaq, A., Imtiaz, F., MaratabZiai, A., Gulzar, A., Farooq, M., Hussain, N., Ahmed, N., Pervez, S., & Zaidi, J. H. (2013). Development of low enriched uranium target plates by thermo-mechanical processing of UAl2–Al matrix for production of 99Mo in Pakistan. J. Nucl. Eng. Des., 255, 77–85. DOI: 10.1016/j.nucengdes.2012.10.014. 4. 4. Burril, K. A., & Harrison, R. J. (1989). Development of the 99Mo process at CRNL. In Fission molybdenum for medical use. Proceedings of Technical Committee Meeting organized by the International Atomic Energy Agency and held in Karlsruhe, 13–16 October 1987 (pp. 35–46). Vienna: International Atomic Energy Agency. (IAEA-TECDOC-515). 5. 5. Arino, H., Kramer, H. H., McGovern, J. J., & Thornton, A. K. (1974). Production of high purity fission product molybdenum-99. U.S. Patent 3,799,883.
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