Download Intro_RAST-K_2.0

The Recommended Publication for Citing

  1. Jiwon Choe, Sooyoung Choi, Peng Zhang, Jinsu Park, Wonkyeong Kim, Ho Cheol Shin, Hwan Soo Lee, Ji-Eun Jung, Deokjung Lee*, “Verification and validation of STREAM/RAST-K for PWR analysis,” Nuclear Engineering and Technology, ISSN 1738-5733, (2018)
  2. Farrokh Khoshahval, Minyong Park, Ho Cheol Shin, and Deokjung Lee*, “Vanadium, Rhodium, Silver and Cobalt Self-Powered Neutron Detector Calculations by RAST-K v2.0,” Annals of Nuclear Energy, 111: 644-659. (2018)


The RAST-K 2.0 code is a recently developed three-dimensional two-group PWR core analysis code by UNIST CORE lab. It aims to be used by utilities to perform in-core fuel management studies, core design calculations, load follow simulation and transient analysis in neutronics. The RAST-K 2.0 code is capable of performing steady-state, quasi transient and transient calculations by solving the two-group three-dimensional neutron diffusion equation in eigenvalue or fixed source modes.


Transverse Integrated Nodal Methods (TINMs)

– Nodal Expansion Method (NEM)

– Analytic Nodal Method (ANM)

– Semi-analytic Nodal Method (SANM)


Non-transverse Integrated Nodal Methods

– Analytic Function Expansion Nadal (AFEN) Method

– Polynomial Expansion Nodal (PEN) Method


Unified Nodal Method

– Integrate the NEM, ANM and AFEN into a single unified nodal formulation



I. Steady State & Transient Nodal Solver

– IAEA PWR 3D Benchmark

– LRA benchmark

– Benchmark tests for transient (LMW benchmark, LRA benchmark, NEACRP benchmark)

II. Micro Depletion

– Shin-Kori Unit-3 Cycle-01 Fuel Assembly Depletion Problem

III. Core Depletion

– Shin-Kori Unit-1

– C0 Type (235U 3.42/2.42%, No Gd)

– SIMULATE-3 use INTERPIN with coefficient table and RAST-K 2.0 use single channel T/H 1-D module for T/H calculation

– SMPWR: Non-Boron Small Modular PWR

IV. Pin Power Reconstruction

– Shin-Kori Unit-1

V. LPPT (Low Power Physics Test)

– Independent Control Rod Worth

– Dependent Control Rod Worth

Shin-Kori Unit-1 Cycle-01 HFP BOC/MOC/EOC


SMPWR Core Calculation Results Comparison


Shin-Kori Unit-3 Cycle-01 Fuel Assembly Depletion Problem