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Cheng C, Xie Y, Xia X, Gu J, Wang P, Xing L, Wang M, Hei D, Lei H, Wenbao J. Neutron collimator optimization for 14.1 MeV DT neutrons using Monte Carlo and Genetic algorithms. Appl Radiat Isot 2023; 198:110838. [PMID: 37182395 DOI: 10.1016/j.apradiso.2023.110838] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 01/12/2023] [Revised: 04/27/2023] [Accepted: 05/04/2023] [Indexed: 05/16/2023]
Abstract
The fast neutrons generated by Deuterium-Tritium (DT) fusion reaction have been widely applied in prompt gamma ray neutron activation analysis measurements. In this study, a multi-layer neutron collimator for DT neutron generator was developed. Genetic algorithm combined with Monte Carlo simulation was used to design a collimator made of iron, lead, graphite, and borated polyethene. Copper foil activations were conducted to determine the fast neutron flux ratios between the beam port and its nearby area and agreed well with those predicted by the simulations. The results demonstrated that a narrower beam was obtained. The fast neutron beam flux was 568 ± 14 s-1 cm-2. The neutron flux ratio of the collimator was improved by a factor of 2.36, which could provide a better neutron beam.
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Affiliation(s)
- Can Cheng
- Jiangsu Institute of Metrology, Nanjing, 210023, China; Institute of Nuclear Analytical Technology, Nanjing University of Aeronautics and Astronautics, Nanjing, 211106, China; Engineering Research Center of Nuclear Technology Application, Ministry of Education, East China University of Technology, Nanchang, 330013, China
| | - YongJi Xie
- China Nuclear Power Engineering Co., Ltd., Beijing, 100840, China
| | - Xunrong Xia
- Jiangsu Institute of Metrology, Nanjing, 210023, China.
| | - Jiayu Gu
- Jiangsu Institute of Metrology, Nanjing, 210023, China
| | - Peng Wang
- Jiangsu Institute of Metrology, Nanjing, 210023, China
| | - Liteng Xing
- Jiangsu Institute of Metrology, Nanjing, 210023, China
| | - Meiyi Wang
- Institute of Nuclear Analytical Technology, Nanjing University of Aeronautics and Astronautics, Nanjing, 211106, China
| | - Daqian Hei
- Institute of Nuclear Analytical Technology, Nanjing University of Aeronautics and Astronautics, Nanjing, 211106, China
| | - Haoyu Lei
- Nuclear Power Institute of China, Chengdu, 610041, China
| | - Jia Wenbao
- Institute of Nuclear Analytical Technology, Nanjing University of Aeronautics and Astronautics, Nanjing, 211106, China.
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Hei D, Jia W, Cheng C, Yao Z, Shan Q, Ling Y, Lei H. Design of an inelastic neutron scattering system based on DT neutron generator for metallic materials analysis. J Radioanal Nucl Chem 2021. [DOI: 10.1007/s10967-021-07755-3] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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3
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He DD, Jing SW, Zheng YL. Design and optimization of thermal neutron device based on deuterium-deuterium neutron generator. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112289] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Cheng C, Wei Z, Hei D, Jia W, Li J, Cai P, Gao Y, Shan Q, Ling Y. MCNP benchmark of a 252Cf source-based PGNAA system for bulk sample analysis. Appl Radiat Isot 2020; 158:109045. [PMID: 31989932 DOI: 10.1016/j.apradiso.2020.109045] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 02/05/2019] [Revised: 01/15/2020] [Accepted: 01/15/2020] [Indexed: 10/25/2022]
Abstract
A MCNP model of a252Cf source-based prompt gamma-ray neutron activation analysis (PGNAA) system for bulk sample analysis was benchmarked. The indium foils activation and aqueous samples containing chlorine were measured using the PGNAA system, and the experimental data compared to the simulations. The discrepancies between the measurements and simulations are within 6% and 20% for thermal neutron flux and prompt gamma-ray response, respectively. The results show that the simulations agree well with the measurements, and demonstrate the proposed MCNP model can represent the system.
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Affiliation(s)
- Can Cheng
- College of Astronautics, Nanjing University of Aeronautics and Astronautics, Nanjing, 211106, China; Collaborative Innovation Center of Radiation Medicine of Jiangsu Higher Education Institutions, Suzhou, 215000, China
| | - Zhiyong Wei
- College of Astronautics, Nanjing University of Aeronautics and Astronautics, Nanjing, 211106, China
| | - Daqian Hei
- Collaborative Innovation Center of Radiation Medicine of Jiangsu Higher Education Institutions, Suzhou, 215000, China; School of Nuclear Science and Technology, Lanzhou University, Lanzhou, 730000, China.
| | - Wenbao Jia
- College of Materials Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing, 211106, China; Collaborative Innovation Center of Radiation Medicine of Jiangsu Higher Education Institutions, Suzhou, 215000, China
| | - Jiatong Li
- College of Materials Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing, 211106, China; Collaborative Innovation Center of Radiation Medicine of Jiangsu Higher Education Institutions, Suzhou, 215000, China
| | - Pingkun Cai
- College of Materials Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing, 211106, China
| | - Youtao Gao
- College of Astronautics, Nanjing University of Aeronautics and Astronautics, Nanjing, 211106, China
| | - Qing Shan
- College of Materials Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing, 211106, China; Collaborative Innovation Center of Radiation Medicine of Jiangsu Higher Education Institutions, Suzhou, 215000, China
| | - Yongsheng Ling
- College of Materials Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing, 211106, China; Collaborative Innovation Center of Radiation Medicine of Jiangsu Higher Education Institutions, Suzhou, 215000, China
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Tantillo F, Mauerhofer E. A priori calculation of the thermal neutron die-away time of large samples irradiated in the facility MEDINA. J Radioanal Nucl Chem 2018. [DOI: 10.1007/s10967-018-5874-5] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Mildenberger F, Mauerhofer E. Cyclic neutron activation analysis of large samples with a pulsed 14 MeV neutron source. J Radioanal Nucl Chem 2016. [DOI: 10.1007/s10967-016-5098-5] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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Nicol T, Mauerhofer E, Carasco C, Perot B, Collot J. HPGe-detector shielding optimization with MCNP for the MEDINA neutron activation cell. J Radioanal Nucl Chem 2016. [DOI: 10.1007/s10967-016-4816-3] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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