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Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Nuclear Science and Engineering
Fusion Science and Technology
What is involved in radiation protection at accelerator facilities?
Particle accelerators have evolved from exotic machines probing hadron interactions to understand the fundamentals of our world to widely used instruments in research and for medical and industrial use. For research purposes, high-power machines are employed, often producing secondary particle beams through primary beam interaction with a target material involving many meters of shielding. The charged beam interacts with the surrounding structures, producing both prompt radiation and secondary radiation from activated materials. After beam termination, some parts of the facility remain radioactive and potentially can become radiation hazards over time. Radiation protection for accelerator facilities involves a range of actions for operation within safe boundaries (an accelerator safety envelope). Each facility establishes fundamental safety principles, requirements, and measures to control radiation exposure to people and the release of radioactive material in the environment.
Deniz Canbula, Bora Canbula
Nuclear Technology | Volume 209 | Number 6 | June 2023 | Pages 895-901
Technical Paper | doi.org/10.1080/00295450.2022.2163802
Articles are hosted by Taylor and Francis Online.
Some isotopes such as 123I and 124I are useful in medical science, and thus, the production of these isotopes has great importance. Iodine-123 is the gamma-emitting radioisotope of radioiodine, and 124I is the long-lived positron-emitting radioisotope of radioiodine, and they have applications in diagnosis via both Single Photon Emission Computed Tomography (SPECT)/Positron Emission Tomography (PET) and radiotherapy. Therefore, many theoretical and experimental studies are performed for these isotopes. In this study, the cross sections of the 123Te(p,n), 124Te(p,n), and 124Te(p,2n) reactions up to 31 MeV, where 123I and 124I can be produced, are calculated by importing the Collective Semi-Classical Fermi Gas Model (CSCFGM) to the Talys 1.96 computer code. The predictions are compared with the default theoretical calculations of Talys 1.96 and existing experimental data taken from the EXFOR library. The results are in good agreement with the experimental data, and therefore, CSCFGM looks to be a useful tool for predicting the production reactions of some therapeutic isotopes.