Pressurized Water Reactors | List of Frontiers open access articles

Original Research

Published on 12 Feb 2025

Reliability analysis of passive residual heat removal system for large advanced pressurized water reactors

in Nuclear Reactor Design

Tianrui Li
Xinkun Xiao
Guoqing Lu
Shikang Chen
Ronghua Chen
Wenxi Tian

Frontiers in Nuclear Engineering

doi 10.3389/fnuen.2025.1516841

1,627 views
3 citations

Review

Published on 16 Apr 2024

Understanding the high-temperature corrosion behavior of zirconium alloy as cladding tubes: a review

in Environmental Degradation of Materials

Yan Tang
Jingjing Liao
Di Yun

Frontiers in Materials

doi 10.3389/fmats.2024.1381818

5,864 views
9 citations

Original Research

Published on 02 Feb 2024

Large eddy simulation of a turbulent flow in a 5 x 5 rod bundle with a mixing vane spacer grid

in Nuclear Energy

Chuan Lu
Zhaohui Du

Frontiers in Energy Research

doi 10.3389/fenrg.2024.1334200

2,360 views
1 citation

Original Research

Published on 25 May 2018

A Hybrid Semi-implicit Method of 1D Transient Compressible Flow for Thermal-Hydraulic Analysis of (V)HTR Gas Turbine Systems

in Nuclear Energy

Jie Wang
Xiaxin Cao
Zhaoming Meng
Jie Wang
Ming Ding

Frontiers in Energy Research

doi 10.3389/fenrg.2018.00044

3,289 views
5 citations

Original Research

Published on 15 Jan 2025

Experimental research on heat transfer characteristics of a two-layer corium pool based on a three-dimensional ellipsoidal lower plenum

in Nuclear Reactor Design

Shihao Wu
Yapei Zhang
Jian Yu
Jingyuan Bai
Wenxi Tian
Suizheng Qiu
G. H. Su

Frontiers in Nuclear Engineering

doi 10.3389/fnuen.2024.1523026

1,239 views

Original Research

Published on 06 Dec 2021

Dynamic Reliability Evaluation of Diesel Generator System of One Chinese 1000MWe NPP Considering Temporal Failure Effects

in Nuclear Energy

Dingqing Guo
Manjiang Yang
Hongmei Wu
Daochuan Ge
Xuewu Cao

Frontiers in Energy Research

doi 10.3389/fenrg.2021.793577

3,744 views
5 citations

Original Research

Published on 27 Aug 2021

Burnable Poison Selection and Neutronics Analysis of Plate Fuel Assemblies

in Nuclear Energy

Shikun Xu
Tao Yu
Jinsen Xie
Lei Yao
Zhulun Li

Frontiers in Energy Research

doi 10.3389/fenrg.2021.729552

4,264 views
4 citations

Original Research

Accepted on 25 Feb 2026

Validation of SIMULATE5-K and CASMO5 with the SPERT-III E-Core

in Nuclear Reactor Design

William Dawn
Gerardo Grandi

Frontiers in Nuclear Engineering

Articles

Reliability analysis of passive residual heat removal system for large advanced pressurized water reactors

Understanding the high-temperature corrosion behavior of zirconium alloy as cladding tubes: a review

Large eddy simulation of a turbulent flow in a 5 x 5 rod bundle with a mixing vane spacer grid

A Hybrid Semi-implicit Method of 1D Transient Compressible Flow for Thermal-Hydraulic Analysis of (V)HTR Gas Turbine Systems

Experimental research on heat transfer characteristics of a two-layer corium pool based on a three-dimensional ellipsoidal lower plenum

Dynamic Reliability Evaluation of Diesel Generator System of One Chinese 1000MWe NPP Considering Temporal Failure Effects

Burnable Poison Selection and Neutronics Analysis of Plate Fuel Assemblies

Validation of SIMULATE5-K and CASMO5 with the SPERT-III E-Core