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- W2137881286 abstract "Abstract The main objective of 235 U irradiation is to obtain the 99m Tc isotope, which is widely used in the domain of medical diagnostics. The decisive factor determining its availability, despite its short lifetime, is a reaction of radioactive decay of 99 Mo into 99m Tc. One of the possible sources of molybdenum can be achieved in course of the 235 U fission reaction. The paper presents activities and the calculation results obtained upon the feasibility study on irradiation of 235 U targets for production of 99 Mo in the MARIA research reactor. Neutronic calculations and analyses were performed to estimate the fission products activity for uranium plates irradiated in the reactor. Results of dummy targets irradiation as well as irradiation uranium plates have been presented. The new technology obtaining 99 Mo is based on irradiation of high-enriched uranium plates in standard reactor fuel channel and calculation of the current fission power generation. Measurements of temperatures and the coolant flow in the molybdenum installation carried out in reactor SAREMA system give online information about the current fission power generated in uranium targets. The corrective factors were taken into account as the heat generation from gamma radiation from neighbouring fuel elements as well as heat exchange between channels and the reactor pool. The factors were determined by calibration measurements conducted with aluminium mock-up of uranium plates. Calculations of fuel channel by means of REBUS code with fine mesh structure and libraries calculated by means of WIMS-ANL code were performed." @default.
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- W2137881286 date "2014-07-08" @default.
- W2137881286 modified "2023-10-05" @default.
- W2137881286 title "Production of Fission Product <sup>99</sup>Mo using High-Enriched Uranium Plates in Polish Nuclear Research Reactor MARIA: Technology and Neutronic Analysis" @default.
- W2137881286 cites W1981526207 @default.
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- W2137881286 doi "https://doi.org/10.2478/nuka-2014-0009" @default.
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