L.B. Fontana , J. Yu , M.P. Short , T. Durak , E. Lamere , M.S. Galanek , A. Safarov , H.M. Wainwright
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引用次数: 0
Abstract
This paper presents a new design and modeling of a rapid, multiple sample Cf-252 irradiator for neutron activation analysis (NAA) to replace research reactor irradiations, with a particular focus on safety analysis associated with neutron and gamma dose rates in areas typically occupied by individuals. The study utilizes the Monte Carlo N-Particle (MCNP6) simulation code to assess three different configurations aimed at optimizing safety and operational efficiency. A252Cf source emitting 5.77 × 107 neutrons per second is considered. Simulations were conducted to determine optimal shielding configurations that comply with established radiation exposure limits. Ricorad™, a borated polyethylene material known for its exceptional neutron shielding performance due to its high hydrogen concentration, was specifically utilized for efficient and lightweight shielding. Additionally, the study examines the distribution of neutron flux around the 252Cf source to ensure optimal sample placement for 75As activation – a key output of planned activation studies. Furthermore, the paper examines practical irradiation applications at this sample position by estimating the measurement time needed to achieve 2000 counts for the 76As peak at 559.101 keV in a sample of coal fly ash using a high-purity germanium detector. The overarching goal of this work is to ensure safe and efficient utilization of a252Cf-based neutron irradiator for NAA, emphasizing the importance of radiation safety while minimizing space requirements and enabling accurate and reliable measurements.
期刊介绍:
Applied Radiation and Isotopes provides a high quality medium for the publication of substantial, original and scientific and technological papers on the development and peaceful application of nuclear, radiation and radionuclide techniques in chemistry, physics, biochemistry, biology, medicine, security, engineering and in the earth, planetary and environmental sciences, all including dosimetry. Nuclear techniques are defined in the broadest sense and both experimental and theoretical papers are welcome. They include the development and use of α- and β-particles, X-rays and γ-rays, neutrons and other nuclear particles and radiations from all sources, including radionuclides, synchrotron sources, cyclotrons and reactors and from the natural environment.
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Papers dealing with radiation processing, i.e., where radiation is used to bring about a biological, chemical or physical change in a material, should be directed to our sister journal Radiation Physics and Chemistry.