B. RAST-K 2.0


The Recommended Publication for Citing
  1. 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. https://doi.org/10.1016/j.anucene.2017.09.048 (2018)
Introduction
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

Verifications
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




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