System Code | List of Frontiers open access articles

Original Research

Published on 15 Aug 2024

Development and validation of ARSAC-CORTH coupling code based on a generic coupling architecture

in Nuclear Energy

Xiaoyu Wang
Zhifang Qiu
Shinian Peng
Jian Deng
Wei Zeng
Luguo Liu
Xilin Zhang
Xue Zhang
Yunfeng Xia
Mingjun Wang

Frontiers in Energy Research

doi 10.3389/fenrg.2024.1400805

1,542 views
1 citation

Original Research

Published on 16 Feb 2024

Development and preliminary verification of a 1D–3D coupled flow and heat transfer model of OTSG

in Nuclear Energy

Xianghui Lu
Xin Wang
Xiong Zheng
Xiting Chen
Shuqi Meng
Tianming Ruan
Jun Chen
Yulong Mao
Yisong Hu
Chaohao Shang

Frontiers in Energy Research

doi 10.3389/fenrg.2024.1368303

2,966 views
4 citations

Original Research

Published on 18 May 2022

Research on Countercurrent Flow Limitation in Reactor Hot Leg at the Loss of Coolant Accident-Thermohydraulic Calculation With System Code RELAP5

in Nuclear Energy

Xiang Li
Lingyuan Gao
Caihong Xu
Ting Wang
Wan Sun
Wen Zhu
Luteng Zhang
Zaiyong Ma
Longxiang Zhu
Liangming Pan

Frontiers in Energy Research

doi 10.3389/fenrg.2022.891105

2,193 views
1 citation

Original Research

Published on 30 Jul 2024

Coupling of the best-estimate system code and containment analysis code and its application to TMLB’ accident

in Nuclear Energy

Xiaoli Wu
Zhifeng Zheng
Jian Deng
Yu Liu
Qi Lu
Qingan Xiang
Chong Chen
Hongping Sun
Yazhe Lu
Danhong Shen

Frontiers in Energy Research

doi 10.3389/fenrg.2024.1436245

1,516 views
1 citation

Original Research

Published on 16 Mar 2015

Thermal-Hydraulic Analysis of SWAMUP Facility Using ATHLET-SC Code

in Nuclear Energy

Zidi Wang
Zhen Cao
Xiaojing Liu

Frontiers in Energy Research

doi 10.3389/fenrg.2015.00011

4,839 views
1 citation

Original Research

Published on 09 Feb 2021

Development and Validation of Multiscale Coupled Thermal-Hydraulic Code Combining RELAP5 and Fluent Code

in Nuclear Energy

Lin Sun
Minjun Peng
Genglei Xia
Xuesong Wang
Mingyu Wu

Frontiers in Energy Research

doi 10.3389/fenrg.2020.613852

3,696 views
5 citations

Original Research

Published on 08 Oct 2021

Using Machine Learning to Predict the Fuel Peak Cladding Temperature for a Large Break Loss of Coolant Accident

in Nuclear Energy

Wazif Sallehhudin
Aya Diab

Frontiers in Energy Research

doi 10.3389/fenrg.2021.755638

5,022 views
23 citations

Articles

Development and validation of ARSAC-CORTH coupling code based on a generic coupling architecture

Development and preliminary verification of a 1D–3D coupled flow and heat transfer model of OTSG

Research on Countercurrent Flow Limitation in Reactor Hot Leg at the Loss of Coolant Accident-Thermohydraulic Calculation With System Code RELAP5

Coupling of the best-estimate system code and containment analysis code and its application to TMLB’ accident

Thermal-Hydraulic Analysis of SWAMUP Facility Using ATHLET-SC Code

Development and Validation of Multiscale Coupled Thermal-Hydraulic Code Combining RELAP5 and Fluent Code

Using Machine Learning to Predict the Fuel Peak Cladding Temperature for a Large Break Loss of Coolant Accident