INCLUDES:

• NJOY91, a code system for producing pointwise and multigroup neutron and photon cross sections from ENDF/B evaluated nuclear data.
  
• MCNP4a, a Monte Carlo code for reactor analysis and design, as well as shielding calculations.
  
• VIM, a Monte Carlo codes for reactor analysis and design.
  
• GTRAN2, a general geometry transport theory code that solves the multigroup steady-state neutron integral transport equation in arbitrary two-dimensional geometries that can be described by combinatorial geometry.
  
• MAGGENTA, a multiprocessor multi-assembly general geometry neutron transport theory code that solves the multigroup steady-state neutron integral transport equation in arbitrary two-dimensional geometries.
  
• TWODANT - one and two-dimensional, multigroup, discrete ordinates transport code system for reactor analysis.
  
• SWAN - a one-dimensional code for the optimization of the nuclear design os source-driven systems, such as radiation shields, fusion reactor blankets, and radiation-based medical facilities.
  
• SCALE 4.3, a code system that performs standardized computer analysis for licensing evaluation. The system is widely used in the US and abroad by government contractors, private industry, and universities to perform: problem-dependent multigroup cross section processing, criticality safety analyses, shielding analyses, heat transfer analyses, and spent fuel and high-level waste characterization.
  
• MICBURN-E, a multigroup pin cell lattice physics computer code designed for burnup analysis of LWR fuel rods.
  
• CPM-2, a lattice physics code which employs two-dimensional, multigroup neutron transport equations to solve for detailed neutron flux distributions and eigenvalues in fuel assembly designs of LWRs.
  
• SIMULATE-E, a three-dimensional steady-state nodal analysis code for calculation of LWRs power distribution, control rod patterns, xenon transients, and reactor cycle length.
  
• RETRAN-03, a transient thermal-hydraulic analysis code with capabilities for: BWR and PWR transients, small break loss-of-coolant accidents, anticipated transients without scram, long-term transients, and transients with thermodynamic nonequilibrium phenomena.
  
• RELAP5, a thermal-hydraulic system simulation code package.
  
• MAGG-SCALE, a state-of-the-art coupling of SCALE 4.3 and MAGGENTA.