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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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.
Codey Olson, Jesse Snow, Meng-Jen (Vince) Wang, Glenn Sjoden, Edward Cazalas
Nuclear Technology | Volume 209 | Number 9 | September 2023 | Pages 1241-1251
Research Article | doi.org/10.1080/00295450.2023.2203291
Articles are hosted by Taylor and Francis Online.
Here we perform the matching of neutron counts in two detector gasses through capture reactions and radiation transport–optimized moderating materials. One of our detectors uses helium-3 (3He) gas and has been widely used as a neutron detection material in proportional detector tube designs. This study examines boron trifluoride (BF3) as a potential gas for neutron detection in place of 3He based on a previously studied “spectrally matched” design derived from deterministic adjoint analyses that closely mimic the spectral response of 3He. The integrated spectral response of each tube, i.e., the count rate, is calculated and measured at various distances from an isotropic neutron source where similar “total sources” are achieved in either detection system. Our results show the integrated spectral response of a dual BF3 tube detector was within 10% of a single 3He tube when exposed to a similar source. GEANT4 Monte Carlo simulations were used to calculate the total source for each detector and showed count rates within 5% of those produced by MCNP, providing a strong confidence in its behavior in the thermal energy regime. We provide results in this study to partially validate the replacement based on the spectrally matched design, which will lead to further validation through the utilization of multiple neutron spectra via simulated and experimental studies.