In Pile | List of Frontiers open access articles

Original Research

Published on 24 Jan 2022

Macro-Mesoscale In-Pile Thermal-Mechanical Behavior Simulation of a UMo/Zr Monolithic Fuel Plate

in Nuclear Energy

Xiangzhe Kong
Xiaobin Jian
Feng Yan
Wenjie Li
Zixuan Guo
Chuan Lu
Shurong Ding
Yuanming Li

Frontiers in Energy Research

doi 10.3389/fenrg.2021.801398

1,783 views
2 citations

Original Research

Published on 19 Dec 2023

In-pile performance of end plug with different structure for SiC cladding

in Energy Materials

Huifang Yue
Shichao Liu
Yong Xin
Yuanming Li
Ping Chen
Xi Qiu

Frontiers in Materials

doi 10.3389/fmats.2023.1321983

3,136 views
1 citation

Original Research

Published on 23 May 2024

A corrosion model for CZ cladding based on in-pile irradiation data

in Nuclear Energy

Xu Duoting
Wei Xiaoyan
Liu Xiaohan
Jin Xin
Wang Tao

Frontiers in Energy Research

doi 10.3389/fenrg.2024.1395354

1,180 views

Methods

Published on 09 Oct 2024

Study on fuel management strategy for accident-tolerant fuel on in-pile irradiation test

in Nuclear Energy

Qingyu Gao
Yuxiang Zhu
Zehua Li
Tianze Jiang
Changyou Zhao

Frontiers in Energy Research

doi 10.3389/fenrg.2024.1463183

1,424 views

Original Research

Published on 11 May 2021

Numerical Simulation Research on the Irradiation-Thermal-Mechanical Performance Evolution of FCM Fuel

in Nuclear Energy

Tang Changbing
Li Yuanming
Jiao Yongjun
Zhang Kun
Wang Peng

Frontiers in Energy Research

doi 10.3389/fenrg.2021.664345

2,792 views
5 citations

Original Research

Published on 09 May 2023

High-temperature irradiation-resistant thermocouple instability model for in-pile reactor use

in Nuclear Energy

Richard Skifton

Frontiers in Energy Research

doi 10.3389/fenrg.2023.1099584

2,735 views
5 citations

Editorial

Published on 01 Jun 2023

Editorial: Experimental and model-based assessment of diffusion kinetics of actinides and oxygen during fuel fabrication and of fission products over in-pile use

in Nuclear Materials

Jacques Léchelle
Lelio Luzzi
Luteng Zhang

Frontiers in Nuclear Engineering

doi 10.3389/fnuen.2023.1214113

1,046 views
1 citation

Articles

Macro-Mesoscale In-Pile Thermal-Mechanical Behavior Simulation of a UMo/Zr Monolithic Fuel Plate

In-pile performance of end plug with different structure for SiC cladding

A corrosion model for CZ cladding based on in-pile irradiation data

Study on fuel management strategy for accident-tolerant fuel on in-pile irradiation test

Numerical Simulation Research on the Irradiation-Thermal-Mechanical Performance Evolution of FCM Fuel

High-temperature irradiation-resistant thermocouple instability model for in-pile reactor use

Editorial: Experimental and model-based assessment of diffusion kinetics of actinides and oxygen during fuel fabrication and of fission products over in-pile use