Investigation of 99Mo potential production via UO2SO4 liquid target irradiation in a 5 MW nuclear research reactor

Gholamzadeh, Zohreh; Mirvakili, Seyed Mohammad; Davari, Amin; Alizadeh, Mosoumeh; Joz-Vaziri, Atieh

doi:10.1515/nuka-2017-0006

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.

References

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.2014.02.013.10.1016/j.apradiso.2014.02.01324657474
Search in Google Scholar Back to article
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/10.1155/2013/932546.10.1155/2013/932546
Search in Google Scholar Back to article
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.2012.10.014.10.1016/j.nucengdes.2012.10.014
Search in Google Scholar Back to article
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).
Search in Google Scholar Back to article
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.
Search in Google Scholar Back to article
6. Youker, A. J., Chemerisov, S. D., Kalensky, M., Tkac, P., Bowers, D. L., & Vandegrift, G. F. (2013). A solution-based approach for Mo-99 production: Considerations for nitrate versus sulfate media. J. Sci. Technol. Nucl. Install., 2013, Article ID 402570, 10 pp. http://dx.doi.org/10.1155/2013/402570.10.1155/2013/402570
Search in Google Scholar Back to article
7. Bennett, M. E., Bowers, D. L., Pereira, C., & Vandegrift, G. F. (2014). Conversion of uranyl sulfate solution to uranyl nitrate solution for processing in UREX. In 2014 Mo-99 Topical Meeting, 24–27 June 2014, Washington D.C. (S9-P1, 11 pp.). Available from http://mo99.ne.anl.gov/2014/pdfs/papers/S9P1%20Paper%20Bennett.pdf.
Search in Google Scholar Back to article
8. Elgin, K. (2014). A study of the feasibility of 99Mo production inside the TU Delft Hoger Onderwijs Reactor, A Monte Carlo serpent analysis of the HOR research reactor and its medical isotope production capabilities using uranium salts. Thesis, Delft University of Technology, The Netherlands.
Search in Google Scholar Back to article
9. Micklich, B. J. (2015). Remanent activation in the mini-SHINE experiments. In 3rd International Workshop on Accelerator Radiation Induced Activation (ARIA’15), 15–17 April 2015, Knoxville, Tennessee, USA (36 pp.). Available from https://public.ornl.gov/neutrons/conf/aria2015/presentations/12%20Remanent%20Activation%20in%20the%20mini-SHINE%20Experiments.pdf.
Search in Google Scholar Back to article
10. May, I., Rios, D., Anderson, A. S., Bitteker, L., Copping, R., Dale, G. E., Dalmas, D. A., Gallegos, M. J., Garcia, E. K., Kelsey, C. T., Mocko, M., Reilly, S. D., Stephens, F. H., Taw, F. L., & Woloshun, K. A. (2013). A technical demonstration of the initial stage of Mo-99 recovery from a low enriched uranium sulfate solution. Los Alamos National Laboratory. (LA-UR-13-28967).10.2172/1107941
Search in Google Scholar Back to article
11. Ball, R. M. (1997). Characteristics of nuclear reactors used for the production of molybdenum-99. In Production technologies for molybdenum-99 and technetium-99m (pp. 5–17). Vienna: International Atomic Energy Agency. (IAEA-TECDOC-1065). Availaible from http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/30/013/30013597.pdf.
Search in Google Scholar Back to article
12. Pelowitz, D. B. (2008). MCNPX User’s Manual. Version 2.6.0.s.l. Los Alamos National Laboratory. (LA-CP-07-1473).
Search in Google Scholar Back to article
13. Fensin, M. L. (2008). Development of the MCNPX depletion capability: A Monte Carlo depletion method that automates the coupling between MCNPX and CINDER90 for high fidelity burnup calculations. Florida University.
Search in Google Scholar Back to article
14. IAEA. (2008). Homogeneous aqueous solution nuclear reactors for the production of Mo-99 and other short lived radioistotopes. Vienna: International Atomic Energy Agency. (IAEA-TECDOC-1601).
Search in Google Scholar Back to article
15. Briesmeister, J. F. (2000). MCNP-A General Monte Carlo N-Particle Transport code Version 4C. Los Alamos National Laboratory. (LA-13709-M).
Search in Google Scholar Back to article
16. Gallmeier, F. X., Iverson, E. B., Lu, W., Ferguson, P. D., Holloway, S. T., Kelsey, Ch., Muhrer, G., Pitcher, E., Wohlmuther, M., & Micklich, B. (2010). The CINDER’90 transmutation code package for use in accelerator applications in combination with MCNPX. In Proceedings of the19th Meeting on Collaboration of Advanced Neutron Sources, March 8–12, 2010 (6 pp.), Grindelwald, Switzerland. Available from http://www.iaea.org/inis/collection/NCLCollection-Store/_Public/46/109/46109595.pdf?r=1.
Search in Google Scholar Back to article
17. Slessarev, I. (2000). Long term radiotoxicity. Lecture given at the Workshop on Nuclear Data and Nuclear Reactors: Physics, Design and Safety, Trieste, 13 March – 14 April, 2000 (LNS015029). Available from http://users.ictp.it/~pub_off/lectures/lns005/Number_2/Slessarev_1.pdf.
Search in Google Scholar Back to article
18. Rijnsdorp, S. (2014). Design of a small Aqueous Homogeneous Reactor for production of 99Mo. M.Sc. Thesis, Delft University of Technology, The Netherlands. Available from http://www.janleenkloosterman.nl/reports/thesis_rijnsdorp_2014.pdf.
Search in Google Scholar Back to article
19. Köster, U. (2011). Present day production of ⁹⁹Mo and alternatives. Grenoble: Institut Laue Langevin.
Search in Google Scholar Back to article
20. Mohammad, A., Mahmood, T., & Iqbal, M. (2009). Fission MOLY production at PARR-1 using LEU plate type target. J. Nucl. Eng. Des., 239, 521–525. DOI: 10.1016/j.nucengdes.2008.11.008.10.1016/j.nucengdes.2008.11.008
Search in Google Scholar Back to article
21. Tárkányi, F., Hermanne, A., Takács, S., Sonck, M., Szücs, Z., Király, B., & Ignatyuk, A. V. (2011). Investigation of alternative production routes of ^99mTc: deuteron induced reactions on ¹⁰⁰Mo. J. Appl. Radiat. Isot., 69, 18–25. DOI: 10.1016/j.apradiso.2010.08.006.10.1016/j.apradiso.2010.08.00620817541
Search in Google Scholar Back to article
22. Ruth, T. J. (2015). The medical isotope crisis: How we got here and where we are going. Vancouver, British Columbia, Canada: TRIUMF and the British Columbia Cancer Agency.
Search in Google Scholar Back to article
23. Jun, B. J., Tanimoto, M., Kimura, A., Hori, N., Izumo, H., & Tsuchia, K. (2010). Feasibility study on mass production of (n,γ)⁹⁹Mo. Japan Atomic Energy Agency. (JAEA-Research 2010-046).
Search in Google Scholar Back to article
24. Rosenthal, G. B., & Lewin, H. C. (2014). Production of 99Mo using high-current alpha beams. In NNSA’s 2014 Mo-99 Topical Meeting, 24–27 June 2014, Washington D.C. Available from http://mo99.ne.anl.gov/2014/pdfs/papers/S11P4%20Paper%20Rosenthal.pdf.
Search in Google Scholar Back to article
25. Faghihian, H., Malekpour, A., & Maragheh, M. G. (2003). Modification of clinoptilolite by surfactants for molibdate (99Mo) adsorption from aqueous solutions. J. Sci. Islamic Republic of Iran, 14, 239–245.
Search in Google Scholar Back to article
26. Stepinski, D. C., Gelis, A. V., Gentner, P., Bakel, A., & Vandegrift, G. F. (2008). Evaluation of Radsorb, Isosorb (Termoxid) and PZC as potential sorbents for separation of ⁹⁹Mo from a homogeneous-reactor fuel solution. In Homogeneous aqueous solution nuclear reactor for the production of Mo-99 and other short lived radioisotopes (pp. 73–80). Vienna: International Atomic Energy Agency. (IAEA-TECDOC-1601). Available from http://www-pub.iaea.org/MTCD/Publications/PDF/te_1601_web.pdf.
Search in Google Scholar Back to article
27. Ling, L., Chung, P. L., Youker, A., Stepinski, D. C., Vandegrift, G. F., & Wang, N. H. L. (2013). Capture chromatography for Mo-99 recovery from uranyl sulfate solutions: Minimum-column-volume design method. J. Chromatogr. A, 1309, 1–14. DOI: 10.1016/j.chroma.2013.08.023.10.1016/j.chroma.2013.08.02323972458
Search in Google Scholar Back to article
28. Dale, G. E., Dalmas, D. A., Gallegos, M. J., Jackman, K. R., Kelsey, C. T., May, I., Reilly, S. D., & Stange, G. M. (2012). 99Mo separation from high-concentration irradiated uranium nitrate and uranium sulfate solutions. J. Ind. Eng. Chem. Res., 51, 13319–13322. DOI: 10.1021/ie3008743.10.1021/ie3008743
Search in Google Scholar Back to article
29. Wu, D., Landsberger, S., Buchholz, B. A., & Vandegrift, G. F. (1994). Processing of LEU targets for ⁹⁹Mo production – testing and modification of the cintichem process. Lecture presented at the 1995 International Meeting on Reduced Enrichment for Research and Test Reactors, September 18–21, 1994, Paris, France. Available from http://www.rertr.anl.gov/MO99/WU95.pdf.
Search in Google Scholar Back to article

Investigation of 99Mo potential production via UO2SO4 liquid target irradiation in a 5 MW nuclear research reactor

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