Nuclear Engineering and Technology

  • 제54권7호
  • /
  • Pages.2572-2578
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  • 2022
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Evaluation of cadmium ratio for conceptual design of a cyclotron-based thermal neutron radiography system

  • Kuo, Weng-Sheng (Nuclear Engineering Division, Institute of Nuclear Energy Research)
  • 투고 : 2021.10.12
  • 심사 : 2022.01.21
  • 발행 : 2022.07.25
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초록

An approximate method for calculating the cadmium ratio of a cyclotron-based thermal neutron radiography system was developed. In this method, the Monte-Carlo code, MCNP6.2, was employed to calculate the neutron capture rates of Au-197, and the cadmium ratio was obtained by computing the ratio of neutron capture rates. From the simulation results, the computed cadmium ratio is reasonably acceptable, and the assumption of ignoring the fast neutron contribution to the cadmium ratio is valid.

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참고문헌

  1. UCANS. http://www.ucans.org.
  2. J.C. Domanus, Practical Neutron Radiography, 1992, ISBN 0792318609.
  3. IAEA, Use of Neutron Beams for Low and Medium Flux Research Reactors: Radiography and Materials Characterization, IAEA-TECDOC-837, 1993.
  4. M.A. Abdou Mandour, et al., Characterization and application of the thermal neutron radiography beam in the Egyptian second experimental and training research reactor (ETRR-2), Science and Technology of Nuclear Installations 2007 (2007), 24180.
  5. Christopher J. Werner, "MCNP User's Manual Code Version 6.2,", LA-UR-17-29981, Los Alamos National Laboratory, 2017.
  6. Dante Marco Zangirolami, et al., Thermal and epithermal neutron fluence rates in the irradiation facilities of the TRIGA IPR-R1 nuclear reactor, Braz. J. Phys. 40 (1) (March, 2010).
  7. ENDF. https://www-nds.iaea.org/exfor/endf.htm.