Recent content by Oliver-BfS

  1. O

    MCNP: How to use value zero in a fully specified fill

    I have just observed that I did not use MCNP6.2 but 6.1 for that problem. (6.2 is not available for me at the moment.) So maybe that feature was newly introduced with version 6.2. However, I cannot find information about that in the 6.2 release notes and the manual of version 6.1 is not...
  2. O

    MCNP: How to use value zero in a fully specified fill

    The MCNP6.2 manual (page 3-37) says: "There are two nj values that can be used in the lattice array that have special meanings. A zero in the level-zero (real world) lattice means that the lattice element does not exist, making it possible, in effect, to specify a non-rectangular array." How...
  3. O

    I Spatial interpolation before or after data processing

    Your understanding of the question is correct. The values cannot be interpolated accurately because ##f(x_i)## is only known at the coordinates ##x_i##. There is no knowledge of the underlying function ##f##. ##f(x_i)## are measured values.
  4. O

    I Spatial interpolation before or after data processing

    Let a set of values at several discrete points in 2D or 3D space be given. These values will be processed by an algorithm. At the end, processed values need not be known at the original locations but at grid points. Therefore, spatial interpolation needs to be applied. Is there a general...
  5. O

    I Number of fission neutrons in ENSDF

    I use ENSDF to get information about gamma energies and emission abundances for various nuclides. Now I need to know data about Cf-252, in particular the abundance of spontaneous fission and the average number of emitted neutrons per fission. Where can I find this information there? Just as a...
  6. O

    Gamma spectrometry: Calibration using X-ray emissions

    The count rates were estimated by fitting Gaussian functions to the peaks. This is done automatically by the software (Canberra's Genie 2000). Summing up the numbers of counts per channel and subtracting the continuum background yields a similar number of counts. Nucleide.org (PDF-File, page 8)...
  7. O

    Gamma spectrometry: Calibration using X-ray emissions

    I have just done an efficiency calibration measurement for the HPGe detector of a whole-body counter. Ba-133 and Eu-152 were the calibration nuclides. For a calibration at low energies I thought of using the X-ray emissions of both nuclides as well. However, the result looks quite bad - see the...
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