Coupled neutronics/thermal-hydraulic analysis of ANTS-100e using MCS/RAST-F two-step code system

• Published in: Nuclear engineering and technology 2023, 55(11), , pp.4048-4056
• Main Authors: Nguyen, Tung Dong Cao, Tran, Tuan Quoc, Lee, Deokjung
• Format: Article
• Language: English
• Subjects: ANTS-100e; Cross-section; LFR; MCS; RAST-F; Thermal-hydraulic; 원자력공학
• ISSN: 1738-5733; 2234-358X
• DOI: 10.1016/j.net.2023.07.020

The feasibility of using the Monte Carlo code MCS to generate multigroup cross sections for nodal diffusion simulations RAST-F of liquid metal fast reactors is investigated in this paper. The performance of the MCS/RAST-F code system is assessed using steady-state simulations of the ANTS-100e core. The results show good agreement between MCS/RAST-F and MCS reference solutions, with a keff difference of less than 77 pcm and root-mean-square differences in radial and axial power of less than 0.5% and 0.25%, respectively. Furthermore, the MCS/RAST-F reactivity feedback coefficients are within three standard deviations of the MCS coefficients. To validate the internal thermal-hydraulic (TH) feedback capability in RAST-F code, the coupled neutronic/TH1D simulation of ANTS-100e is performed using the case matrix obtained from MCS branch calculations. The results are compared to those obtained using the MARS-LBE system code and show good agreement with relative temperature differences in fuel and coolant of less than 0.8%. This study demonstrates that the MCS/RAST-F code system can produce accurate results for core steady-state neutronic calculations and for coupled neutronic/TH simulations.