B. 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, https://doi.org/10.1016/j.net.2018.10.004 (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. 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
III. Core Depletion
IV. Pin Power Reconstruction
V. LPPT (Low Power Physics Test)

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