origen_neutron_options Type Reference

options for neutron calculations printout More...

Public Attributes

integer ngroups
 number of neutron groups More...
 
real(c_double), dimension(:), allocatable bounds
 Energy group boundaries (descending MeV) More...
 
integer nag
 Number of (a,n) bins. More...
 
integer anmedium
 Medium for (a,n) calculations. More...
 
real(c_double) ncut
 Cutoff for (a,n) calculations. More...
 
integer nstar
 Time step for the problem-specific. More...
 
logical print_summary
 Print summary. More...
 
logical print_spectra
 Print spectra. More...
 
logical print_detailed
 Print detailed neutron source information. More...
 
logical enabled
 Enable the calculation. More...
 

Detailed Description

options for neutron calculations printout

Member Data Documentation

integer ngroups

number of neutron groups

real(c_double), dimension(:), allocatable bounds

Energy group boundaries (descending MeV)

integer nag

Number of (a,n) bins.

integer anmedium

Medium for (a,n) calculations.

real(c_double) ncut

Cutoff for (a,n) calculations.

integer nstar

Time step for the problem-specific.

logical print_summary

Print summary.

logical print_spectra

Print spectra.

logical print_detailed

Print detailed neutron source information.

logical enabled

Enable the calculation.


The documentation for this type was generated from the following file: