The Experts below are selected from a list of 13854 Experts worldwide ranked by ideXlab platform
Sheldon Landsberger - One of the best experts on this subject based on the ideXlab platform.
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An online Neutron Activation Analysis database (NAADB)
Journal of Radioanalytical and Nuclear Chemistry, 2020Co-Authors: Mete Bayrak, Sheldon Landsberger, Michael D GlascockAbstract:An online computer program for an interactive database was specifically developed for Neutron Activation Analysis (NAA). The software written in Java includes gamma-ray catalog, Neutron Activation calculator for activity calculations and decay schemes. For the novice, expert and educator this program can greatly reduce needed information in NAA.
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An E-learning tool as living book for knowledge preservation in Neutron Activation Analysis
Journal of Radioanalytical and Nuclear Chemistry, 2020Co-Authors: Borut Smodiš, P Bode, Nuno Pessoa Barradas, Danas Ridikas, Sheldon LandsbergerAbstract:The International Atomic Energy Agency (IAEA) has implemented a detailed E-learning on-line course in Neutron Activation Analysis (NAA). Existing books and guidance documents on the concepts and execution of NAA are out of date and not sufficient anymore to ensure the transfer of current knowledge on its practice. The overall objective of the E-learning tool in NAA is to realize a ‘living book’, summarizing the basic concepts and providing practical information on the implementation of the methodologies which can be more easily updated than a common book, allowing also for visualization using contemporary media.
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characterization of bauxite residue red mud for 235u 238u 232th and 40k using Neutron Activation Analysis and the radiation dose levels as modeled by mcnp
Journal of Environmental Radioactivity, 2017Co-Authors: Sheldon Landsberger, A Sharp, S Wang, Yiannis Pontikes, Alan H TkaczykAbstract:This study employs thermal and epithermal Neutron Activation Analysis (NAA) to quantitatively and specifically determine absorption dose rates to various body parts from uranium, thorium and potassium. Specifically, a case study of bauxite residue (red mud) from an industrial facility was used to demonstrate the feasibility of the NAA approach for radiological safety assessment, using small sample sizes to ascertain the activities of 235U, 238U, 232Th and 40K. This proof-of-concept was shown to produce reliable results and a similar approach could be used for quantitative assessment of other samples with possible radiological significance. 238U and 232Th were determined by epithermal and thermal Neutron Activation Analysis, respectively. 235U was determined based on the known isotopic ratio of 238U/235U. 40K was also determined using epithermal Neutron Activation Analysis to measure total potassium content and then subtracting its isotopic contribution. Furthermore, the work demonstrates the application of Monte Carlo Neutral-Particle (MCNP) simulations to estimate the radiation dose from large quantities of red mud, to assure the safety of humans and the surrounding environment. Phantoms were employed to observe the dose distribution throughout the human body demonstrating radiation effects on each individual organ.
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characterization of bauxite residue red mud for 235 u 238 u 232 th and 40 k using Neutron Activation Analysis and the radiation dose levels as modeled by mcnp
Journal of Environmental Radioactivity, 2017Co-Authors: Sheldon Landsberger, A Sharp, S Wang, Yiannis Pontikes, Alan H TkaczykAbstract:This study employs thermal and epithermal Neutron Activation Analysis (NAA) to quantitatively and specifically determine absorption dose rates to various body parts from uranium, thorium and potassium. Specifically, a case study of bauxite residue (red mud) from an industrial facility was used to demonstrate the feasibility of the NAA approach for radiological safety assessment, using small sample sizes to ascertain the activities of 235U, 238U, 232Th and 40K. This proof-of-concept was shown to produce reliable results and a similar approach could be used for quantitative assessment of other samples with possible radiological significance. 238U and 232Th were determined by epithermal and thermal Neutron Activation Analysis, respectively. 235U was determined based on the known isotopic ratio of 238U/235U. 40K was also determined using epithermal Neutron Activation Analysis to measure total potassium content and then subtracting its isotopic contribution. Furthermore, the work demonstrates the application of Monte Carlo Neutral-Particle (MCNP) simulations to estimate the radiation dose from large quantities of red mud, to assure the safety of humans and the surrounding environment. Phantoms were employed to observe the dose distribution throughout the human body demonstrating radiation effects on each individual organ.
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the simultaneous determination of 235u and 239pu using delayed Neutron Activation Analysis
Journal of Radioanalytical and Nuclear Chemistry, 2013Co-Authors: R Kapsimalis, David C Glasgow, Brian B Anderson, Sheldon LandsbergerAbstract:Delayed Neutron Activation Analysis (DNAA) remains one of the most sensitive methods of nondestructively determining fissile materials in a variety of sample matrices, provided that the samples contain only a single fissile component. This has historically been the limiting factor in many applications of DNAA, and often chemically destructive methods of Analysis have needed to be utilized for many real-world samples. This work seeks to develop a method that will allow for DNAA to be utilized on samples containing multiple fissile components. Initial efforts, presented here, show that using a multivariate linear regression model to describe the delayed Neutron emission profile of an irradiated sample allows for the concurrent determination of fissile nuclides in samples containing both 235U and 239Pu, without chemical separations and using only a single counting step.
Alan H Tkaczyk - One of the best experts on this subject based on the ideXlab platform.
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characterization of bauxite residue red mud for 235u 238u 232th and 40k using Neutron Activation Analysis and the radiation dose levels as modeled by mcnp
Journal of Environmental Radioactivity, 2017Co-Authors: Sheldon Landsberger, A Sharp, S Wang, Yiannis Pontikes, Alan H TkaczykAbstract:This study employs thermal and epithermal Neutron Activation Analysis (NAA) to quantitatively and specifically determine absorption dose rates to various body parts from uranium, thorium and potassium. Specifically, a case study of bauxite residue (red mud) from an industrial facility was used to demonstrate the feasibility of the NAA approach for radiological safety assessment, using small sample sizes to ascertain the activities of 235U, 238U, 232Th and 40K. This proof-of-concept was shown to produce reliable results and a similar approach could be used for quantitative assessment of other samples with possible radiological significance. 238U and 232Th were determined by epithermal and thermal Neutron Activation Analysis, respectively. 235U was determined based on the known isotopic ratio of 238U/235U. 40K was also determined using epithermal Neutron Activation Analysis to measure total potassium content and then subtracting its isotopic contribution. Furthermore, the work demonstrates the application of Monte Carlo Neutral-Particle (MCNP) simulations to estimate the radiation dose from large quantities of red mud, to assure the safety of humans and the surrounding environment. Phantoms were employed to observe the dose distribution throughout the human body demonstrating radiation effects on each individual organ.
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characterization of bauxite residue red mud for 235 u 238 u 232 th and 40 k using Neutron Activation Analysis and the radiation dose levels as modeled by mcnp
Journal of Environmental Radioactivity, 2017Co-Authors: Sheldon Landsberger, A Sharp, S Wang, Yiannis Pontikes, Alan H TkaczykAbstract:This study employs thermal and epithermal Neutron Activation Analysis (NAA) to quantitatively and specifically determine absorption dose rates to various body parts from uranium, thorium and potassium. Specifically, a case study of bauxite residue (red mud) from an industrial facility was used to demonstrate the feasibility of the NAA approach for radiological safety assessment, using small sample sizes to ascertain the activities of 235U, 238U, 232Th and 40K. This proof-of-concept was shown to produce reliable results and a similar approach could be used for quantitative assessment of other samples with possible radiological significance. 238U and 232Th were determined by epithermal and thermal Neutron Activation Analysis, respectively. 235U was determined based on the known isotopic ratio of 238U/235U. 40K was also determined using epithermal Neutron Activation Analysis to measure total potassium content and then subtracting its isotopic contribution. Furthermore, the work demonstrates the application of Monte Carlo Neutral-Particle (MCNP) simulations to estimate the radiation dose from large quantities of red mud, to assure the safety of humans and the surrounding environment. Phantoms were employed to observe the dose distribution throughout the human body demonstrating radiation effects on each individual organ.
Kyuseok Song - One of the best experts on this subject based on the ideXlab platform.
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applications of prompt gamma ray Neutron Activation Analysis detection of illicit materials
Applied Spectroscopy Reviews, 2009Co-Authors: Kyuseok SongAbstract:Abstract Prompt gamma ray Neutron Activation Analysis (PGNAA) is an efficient nondestructive multi-elemental detection technique for samples such as metals, coal (mineral), cement, and radioactive materials as well as for explosives, chemical warfare agents, various narcotics, land mines, etc. The technique can be used in the laboratory or for on-site Analysis for various samples. In addition, the PGNAA technique in elemental Analysis can provide more accurate detection results with low false alarm in variety of application fields when combined with image scanning and chemometric treatment of the obtained data. The development of small-sized Neutron generators enabled and widened these applications because a stationary nuclear reactor is no longer an indispensible element in PGNAA.
J B Yang - One of the best experts on this subject based on the ideXlab platform.
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prompt gamma Neutron Activation Analysis for multi element measurement with series samples
Laser Physics Letters, 2013Co-Authors: J B Yang, Yigang Yang, Xianguo Tuo, Y Cheng, Y F Mou, W Q HuangAbstract:The on-line prompt gamma Neutron Activation Analysis (PGNAA) system is used to measure a series of prepared experimental samples to obtain the prompt characteristic γ-rays of the elements Ca, Fe, Si, Al, Mg and S in the examples of SiO2, Al2O3, MgO, CaO (powder), CaO (block), CaCO3, Fe2O3, Fe3O4 and S. The γ-ray energies are: Si, 3.54 or 4.93 MeV; Ca, 4.42 or 6.42 MeV; S, 5.42 MeV; Fe, 5.92 or 7.63 MeV. Meanwhile, the prompt γ-rays of the main elements are measured in an experiment in which SiO2, Al2O3, MgO, CaO (powder), CaO (block), CaCO3, Fe2O3, Fe3O4 and S are blended to constitute a cement sample. The prompt γ-rays of S will contribute more with increase in S mass, as known from the experiment concerning the prompt γ-ray spectrum for different masses of S.
A Sharp - One of the best experts on this subject based on the ideXlab platform.
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characterization of bauxite residue red mud for 235u 238u 232th and 40k using Neutron Activation Analysis and the radiation dose levels as modeled by mcnp
Journal of Environmental Radioactivity, 2017Co-Authors: Sheldon Landsberger, A Sharp, S Wang, Yiannis Pontikes, Alan H TkaczykAbstract:This study employs thermal and epithermal Neutron Activation Analysis (NAA) to quantitatively and specifically determine absorption dose rates to various body parts from uranium, thorium and potassium. Specifically, a case study of bauxite residue (red mud) from an industrial facility was used to demonstrate the feasibility of the NAA approach for radiological safety assessment, using small sample sizes to ascertain the activities of 235U, 238U, 232Th and 40K. This proof-of-concept was shown to produce reliable results and a similar approach could be used for quantitative assessment of other samples with possible radiological significance. 238U and 232Th were determined by epithermal and thermal Neutron Activation Analysis, respectively. 235U was determined based on the known isotopic ratio of 238U/235U. 40K was also determined using epithermal Neutron Activation Analysis to measure total potassium content and then subtracting its isotopic contribution. Furthermore, the work demonstrates the application of Monte Carlo Neutral-Particle (MCNP) simulations to estimate the radiation dose from large quantities of red mud, to assure the safety of humans and the surrounding environment. Phantoms were employed to observe the dose distribution throughout the human body demonstrating radiation effects on each individual organ.
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characterization of bauxite residue red mud for 235 u 238 u 232 th and 40 k using Neutron Activation Analysis and the radiation dose levels as modeled by mcnp
Journal of Environmental Radioactivity, 2017Co-Authors: Sheldon Landsberger, A Sharp, S Wang, Yiannis Pontikes, Alan H TkaczykAbstract:This study employs thermal and epithermal Neutron Activation Analysis (NAA) to quantitatively and specifically determine absorption dose rates to various body parts from uranium, thorium and potassium. Specifically, a case study of bauxite residue (red mud) from an industrial facility was used to demonstrate the feasibility of the NAA approach for radiological safety assessment, using small sample sizes to ascertain the activities of 235U, 238U, 232Th and 40K. This proof-of-concept was shown to produce reliable results and a similar approach could be used for quantitative assessment of other samples with possible radiological significance. 238U and 232Th were determined by epithermal and thermal Neutron Activation Analysis, respectively. 235U was determined based on the known isotopic ratio of 238U/235U. 40K was also determined using epithermal Neutron Activation Analysis to measure total potassium content and then subtracting its isotopic contribution. Furthermore, the work demonstrates the application of Monte Carlo Neutral-Particle (MCNP) simulations to estimate the radiation dose from large quantities of red mud, to assure the safety of humans and the surrounding environment. Phantoms were employed to observe the dose distribution throughout the human body demonstrating radiation effects on each individual organ.