Abstract
Various substances in the target room of 70-MeV proton beam irradiation facility must be managed as radioactive waste owing to their activation during operations. In radioactive waste management, it is important to calculate the storage period. Consequently, radionuclides of activated substances and radioactivity concentration must be investigated. This study investigated the radionuclides and radioactivity values of activated aluminum, concrete, stainless steel, and each concrete by depth using computational simulations (Monte Carlo N-Particle, FISPACT-II) and measurements. Most of the radionuclides and radioactivity values of the substances obtained by the two methods exceeded the clearance level. For nuclides exceeding the clearance level, the ratio of the FISPACT-II to measurement results yielded an average of 1.21. With increase in the depth of the concrete, the difference between the two results increased. For all substances, the period of satisfying the clearance criterion was more than 10 years. This long period is attributed to the effects of long half-life nuclides 22Na and 54Mn. Thus, when calculating the storage period for radioactive waste disposal, the method resulting in higher activity values for 22Na and 54Mn should be applied.
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Acknowledgements
This work was supported by the Rare Isotope Science Project of the Institute for Basic Science funded by the Ministry of Science and ICT and NRF of the Republic of Korea (2013M7A1A1075764), and the research foundation of Korea University
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Baek, B., Kim, S. & Yang, H. Activation evaluation of substances around the target in 70-MeV proton beam irradiation facilities. J. Korean Phys. Soc. 82, 1124–1139 (2023). https://doi.org/10.1007/s40042-023-00803-z
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DOI: https://doi.org/10.1007/s40042-023-00803-z