7. UNUSUAL FEATURES OF THE PROGRAM
(a) Non-homogeneous boundary conditions.
(b) Fixed source calculation.
(c) Convergence on search quantity as well as on eigenvalue of source.
(d) Transverse buckling calculated or input as constant, group-dependent, region-dependent or group- and region-dependent.
(e) Option to use source from previous case to start iteration.
(f) Numerous printing options.
(g) Data edits include flux normalization, peak-to-average power, median fission energy, median flux energy, mass fissile elements, breeding ratio by region and by reactor, neutron balance and reaction rates, mass and reaction rates by element, by region and reactor, integrated fluxes, median fission, absorption and flux energy by mesh point, total buckling punchout for AILMOE (NESC Abstract 147).
(h) Group- or group- and region-dependent fission spectrum.
(i) Adjoint flux calculation.
(j) Perturbation calculation using the PERT4 code (NESC Abstract 304).
(k) Nine different criticality searches.
(l) Transport correction to diffusion coefficient.
(m) Microscopic cross section library.
(n) Input of microscopic and/or macroscopic cross sections.
(o) Preparation of homogenized materials by cell calculation.
(p) Resonance cross section calculation by ARES2 or by table interpolation in cell and/or reactor calculation.
(q) Material-dependent cross section tape providing a different microscopic cross section library for each material.
(r) Multiple case feature - only changes to previous case are required. Cell calculation can be rerun as well as reactor problems.