Thermal neutron self-shielding correction factors for large sample instrumental neutron activation analysis using the MCNP code |
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| Affiliation: | 1. NCSR Demokritos, Institute of Nuclear Technology and Radiation Protection, P.O. Box 60228, 15310 Aghia Paraskevi, Attikis, Greece;2. Medical Physics Laboratory, Medical School, University of Ioannina, Ioannina 45110, Greece;1. Safeguards & Security Technology (SST), Global Nuclear Security Technology Division, PO Box 2008, Bldg 5700, MS-6166, Oak Ridge, TN 37831-6166, USA;2. Safeguards Science & Technology Group (NEN-1), Nuclear Engineering and Nonproliferation Division, MS-E540, Los Alamos, NM 87545, USA;1. Institute of Nuclear Analytical Technology, College of Materials Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 211106, China;2. School of Nuclear Science and Technology, Lanzhou University, Lanzhou 730000, China;3. Shandong Huate Magnet Technology Co., Ltd, Shandong Province 262600, China;4. Nanjing Instantly Measure Co.,Ltd, Nanjing 211106, China;1. Cyclotron Laboratory, Vrije Universiteit Brussel, Brussels, Belgium;2. Institute of Nuclear Research of the Hungarian Academy of Sciences, Debrecen, Hungary;1. Department of Nuclear Science & Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing, China;2. Jiangsu Key Laboratory of Nuclear Energy Equipment Materials Engineering, China;3. ZhongXing Energy Equipment Co., LTD, Haimen Nantong, China;1. Nagoya University, Nagoya 464-8603, Japan;2. National Institute for Fusion Science, National Institutes of Natural Sciences, Toki 509-5292, Japan;3. SOKENDAI (The Graduate University for Advanced Studies), Toki 509-5292, Japan |
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| Abstract: | Thermal neutron self-shielding within large samples was studied using the Monte Carlo neutron transport code MCNP. The code enabled a three-dimensional modeling of the actual source and geometry configuration including reactor core, graphite pile and sample. Neutron flux self-shielding correction factors derived for a set of materials of interest for large sample neutron activation analysis are presented and evaluated. Simulations were experimentally verified by measurements performed using activation foils. The results of this study can be applied in order to determine neutron self-shielding factors of unknown samples from the thermal neutron fluxes measured at the surface of the sample. |
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