5.3.19.9. Energy distribution of tally results

e-type = 20 : An energy distribution can be specified by using results of tallies by setting the file name with file =.

Only the tally results obtained with axis = eng in [t-track], [t-cross], [t-point], [t-product], [t-time], and [t-interact] can be used. Write in file = the output file name specified in each tally, such as ***.out.

The distributions obtained from the tallies are classified into differential and integrated forms depending on the value of unit =, and the same format is used when they are employed as the source energy distribution. However, the differentials with respect to time (nsec) and angle (sr) are not considered. Only the relative ratios of the distribution are used, and the source weight is set to 1.

When the energy distribution of heavy ions is used as the source, the result becomes shifted in the default setting because the energy unit of the tally result is MeV while that of the source is MeV/n. Therefore, set IMeVperN = 1 in the [parameters] section of the first calculation, that is, the calculation used to output the energy distribution, so that the tally result is also written in MeV/n.

file = : Output file name of the tally.

The distribution used as the source is the result of the first particle specified by part = in obtaining the tally result. Note, however, that the particle itself is not generated as the source particle. The type of particle to be generated as the source is specified by proj =.

An input example is shown below. This function is available by specifying e-type = 20 and file =.

[ Source ]
  s-type =   1        # axial source with energy spectrum
    proj =  neutron   # kind of incident particle
    dir =   1.0       # z-direction of beam [cosine]
    r0 =    0.        # radius [cm]
    z0 =    0.        # minimum position of z-axis [cm]
    z1 =    0.        # maximum position of z-axis [cm]
    e-type = 20       # energy distribution given by tally output
    file = cross.out  # file name of tally output