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Introduction

 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).

Features

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

Depletion
– Matrix exponential method
– Chebyshev rational approximation method
– Chain with ~1400 isotopes
– Predictor/corrector

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

 Pin-based Slowing-down Method (PSM)

2

 Inflow transport correction

1

 Method of Characteristics

3

Benchmark

LWR core plot by STREAM

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STREAM Pin power distribution

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B&W critical Benchmark

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Mosteller Benchmark

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