MCNP6 code in source-detector solid angle calculation


  • Roos Sophia de Freitas Dam Instituto de Engenharia Nuclear
  • William Luna Salgado UFRJ
  • Alessandra Galvão Menezes dos Santos CENS, IEN
  • Renato Raoni Werneck Affonso DIRA, IEN
  • César Marques Salgado DIRA, IEN


Nuclear techniques based on the attenuation of gamma radiation are used in the industry to calculate flow rate, determine fluid density, predict inorganic scale in oil pipelines, evaluate industrial mixers, among other applications. In order to use these nuclear techniques is necessary to perform studies of important parameters of radioactive source and radiation detectors, which are part of the measurement geometry, such as detection efficiency and solid angle. The aim of this report is to calculate the solid angle subtended by a hypothetical detector using the MCNP6 code [1]. The results of the simulations were compared with reference results found in the literature using relative error (RE%). These cases were simulated using a 137Cs (662 keV) point isotropic source (4-?) and an upright circular cylinder. The detector has 10 mm of radius and 20 mm of length. The source is placed in six different positions (S0, S1, S2, S3, S4 and S5) as follows Figure 1 [2].

The solid angle (?) values of source positions in the collinear axis of the detector (S3 and S4) were compared to Equation 1, where d is the distance source-detector and R is radius of the detector, as follows Table 1.

The values of the solid angles calculated by means of the MCNP6 and compared to the literature are in Table 2. Column ?1 represents the values of MCNP6 tally card F1 and column ?2 are the values obtained by Masket et al. (1956) [3]. It is important to note that in positions S0, S3 and S4 the detector was set to a disk shape.

These results indicate that the proposed methodology is able to calculate the solid angle in agreement with the values found in the literature. More information can be found in DAM et al., (2019) [2].




Como Citar

Dam, R. S. de F., Luna Salgado, W., Menezes dos Santos, A. G., Werneck Affonso, R. R., & Marques Salgado, C. (2021). MCNP6 code in source-detector solid angle calculation. Instituto De Engenharia Nuclear: Progress Report, (4). Recuperado de



Application of Nuclear Techniques in Industry