Download Intro_STREAM
A neutron transport analysis code, STREAM (Steady state and Transient REactor Analysis code with Method of Characteristics), has been developed to perform a whole LWR core calculation with the direct transport analysis method and the two-step method. Numerous advanced features, especially resonance treatment methods, have been developed and implemented in the STREAM code for higher accuracy and performance. STREAM with the advanced methods has order of ~100 pcm accuracy in LWR analyses. STREAM has capabilities to analyze the whole LWR core through the two-step (with PARCS or RAST-K 2.0) method and direct transport method (2-D).

Multi-group Cross-Section Generation
 Pin-based pointwise energy slowing-down method
 Equivalence theory for structure material
 Resonance upscattering correction
 Enhanced neutron current method
 Resonance interference factor library method (option)
 Inflow transport correction

Transport Solver
 Method of Characteristics
 T-Y optimum quadrature sets
 Assembly modular ray tracing method
 Direct neutron path linking method
  P0~P5 scattering source treatment
 Coarse mesh finite difference acceleration

 Matrix exponential method
 Chebyshev rational approximation method
 Chain with ~1400 isotopes

Few-group Constants Generation
 Discontinuity factor
 Two-group cross-sections
 Critical spectrum with fundamental mode calculation

Pin-based Slowing-down Method (PSM)

Method of Characteristics

LWR core plot by STREAM

STREAM Pin power distribution

B&W Critical Benchmark

Mosteller Benchmark