NJOY-91
NJOY is a nuclear cross section processing system
Location: /usr/codes/njoy91
Other sources of information:
This is the 1991 release of the NJOY Nuclear Data Processing
System. It includes many bug fixes, major improvements in several
modules (especially matxsr and acer), and some new capabilities
(see resxsr, wimsr, mixr, and purr). The capabilities for
processing ENDF-6 files are almost complete.
NJOY is a system of processing modules intended to convert
evaluated nuclear data in the endf format into forms useful
for practical applications.
- reconr
- reconstruct pointwise cross sections from endf/b
resonance parameters and interpolation schemes.
- broadr
- doppler broaden and thin pointwise cross sections.
- unresr
- compute effective pointwise self-shielded cross
sections in the unresolved energy range.
- heatr
- compute heat production cross sections (kerma)
and damage energy production.
- thermr
- generate neutron scattering cross sections and
point-to-point scattering kernels in the thermal range
for free or bound atoms.
- groupr
- generate self-shielded multigroup cross sections and
group-to-group scattering and photon production matrices.
- gaminr
- compute multigroup photon interaction cross sections,
scattering matrices, and heat production.
- errorr
- construct multigroup covariance matrices.
- covr
- process covariance data from error.
- moder
- convert between endf/b standard coded mode and the
ocked binary mode.
- dtfr
- output and plot multigroup data for discrete ordinates
transport codes.
- ccccr
- format multigroup data into the cccc standard
interface files isotxs, brkoxs, and dlayxs.
- matxsr
- convert multigroup data into the comprehensive matxs
cross section interface format.
- resxsr
- prepare a cccc-like file of pointwise resonance
cross sections for thermal flux calculations.
- acer
- prepare library for the los alamos continuous energy
monte-carlo code mcnp.
- powr
- convert multigroup data into libraries for the thermal
powr reactor codes epri-cell and epri-cpm.
- wimsr
- convert multigroup data into libraries for the
reactor assembly codes wims-d or wims-e.
- plotr
- plot endf, pendf, gendf, or exp. cross sections,
distributions, or matrices.
- mixr
- mix file 3 cross sections (for example, to make
elemental cross sections) for plotting, etc.
- purr
- generate unresolved-resonance probability tables
for the mcnp monte carlo code.