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CODES

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Overview

Home CODES

Codes that we developed

SNURPL has established its own core analysis system from cross-section library generation to neutron transport calculation codes. Each code used novel methodologies and led the research field.
Title Link
nTRACER neutron-TRACER Detail
RENUS Reactor Numerical Simulator Reactor Numerical Simulator Detail
PRAGMA Power Reactor Analysis using GPU-based Monte Carlo Algorithm Detail
SPHINCS SP3 Pin-Homogenized Innovative Neutronic CoreSimulator Detail
ESCOT Efficient Simulator for Core Thermal-Hydraulics Detail
EXUS Effective Xsection Generator based on Ultra-fine Slowing-down Calculation Detail
FEDONA Finite Element Discrete Ordinate Neutronic Analysis
SHAFE SP3 Hexagonal Analysis based on Finite Element
ARTOS Advanced Reactor Transient Operation Simulator
FREK Fast Reactor Kinetics
PRIDE Probabilistic Reactor Investigator with Discretized Energy
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