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

Author:

Nguyen Tung Dong CaoORCID,Tran Tuan Quoc,Lee DeokjungORCID

Funder

Korea Institute of Energy Technology Evaluation and Planning

Ministry of Trade, Industry and Energy

Ministry of Science, ICT and Future Planning

National Research Foundation of Korea

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference28 articles.

1. Extension of the DYN3D/ATHLET code system to SFR applications: models description and initial validation;Fridman;Ann. Nucl. Energy,2023

2. A multiphysics simulation suite for liquid metal-cooled fast reactors;Dawn;Ann. Nucl. Energy,2021

3. Impact of thermal-hydraulic feedback and differential thermal expansion on European sodium-cooled fast reactor core power distribution;Lindley;J. Nucl. Eng. Radiat. Sci.,2023

4. Coupled neutronics thermal-hydraulics analysis using Monte Carlo and sub-channel codes;Vazquez;Nucl. Eng. Des.,2012

5. Neutronics and thermal-hydraulics coupling analysis for a small lead-based fast reactor based on the discrete ordinate nodal and parallel channel method;Fang;Front. Energy Res.,2023

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