STREAM 3D

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The Recommended Publication for Citing

• 1. Sooyoung Choi, Changho Lee, Deokjung Lee*, “Resonance Treatment using Pin-Based Pointwise Energy Slowing-Down Method,” J. Comput. Phys., 330: 134-155. http://dx.doi.org/10.1016/j.jcp.2016.11.007  (2017)

  2. Sooyoung Choi, Deokjung Lee*, "Three-Dimensional Method of Characteristics/Diamond-Difference Transport Analysis Method in STREAM for Whole-core Neutron Transport Calculation," Comput. Phys. Commun., 260:107332, https://doi.org/10.1016/j.cpc.2020.107332 (2021)

  3. Anisur Rahman, Hyun Chul Lee, Deokjung Lee*, “High Fidelity Transient Solver in STREAM based on Multigroup Coarse-Mesh Finite Difference Method,” Nucl. Eng. Tech., 55(9): 3301-3312, https://doi.org/10.1016/j.net.2023.05.019 (2023)

  4. Anisur Rahman, Hyun Chul Lee*, Deokjung Lee*, “High Fidelity Transient Analysis with STREAM based on the Predictor-Corrector Quasi-Static Method," Nucl. Sci. Eng., 198: 545-564, https://doi.org/10.1080/00295639.2023.2194219 (2024)

Introduction

A neutron transport analysis code, STREAM 3D (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. Numerous advanced features, especially resonance treatment methods, hybrid of MPI and OpenMP, have been developed and implemented in the STREAM 3D code for higher accuracy and performance. STREAM 3D with the advanced methods has capabilities to analyze the 3D whole LWR core direct transport method.

Features

Direct 3D core design

– 3D MOC-DD method

– Hybrid MPI/OPENMP parallelization

– Thermal expansion

– Fuel assembly shuffling/refueling

– Thermal-hydraulics (TH) feedback

– Equilibrium Xe feedback & Critical boron concentration search

– Critical control rod search for SBF (soluble boron free) reactor

– Transient calculation based on CMFD and PCQM

Multi-physics

– Gamma contribution to power with gamma transport

– STREAM3D coupled with CTF/FRAPCON

– STREAM3D coupled with CUPID

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

–  Assembly-wise domain decomposition

– Axially-Radially node-wise domain decomposition

Depletion

– Matrix exponential method

– Chebyshev rational approximation method

– Chain with ~1400 isotopes

– Predictor/corrector

3D Whole core Modelling

Functions for multi-cycle operation (restarting/unfolding/shuffling/reloading)

Benchmark: BEAVRS HFP simulation

Multi-physics coupling with CTF/FRAPCON

Rod Ejection Analysis - SPERT III E-Core