Penghui Lei
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Penghui Lei has a total of 73 co-authors. Here are the top co-authors by number of shared publications:
- Chao Ye
Institute of Clean Energy, Yangtze River Delta Research Institute, Northwestern Polytechnical University, Taicang 215400, China
4 shared publications Di Yun
3 shared publications- Di Yun
School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
3 shared publications - Jie Qiu
School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
3 shared publications Ni Jiang
3 shared publicationsPan Qi
3 shared publications
Latest Publications
- Open Access
- 7 March 2025
- Published by MDPI AG in Nanomaterials
- Vol. 15 (6) , 413
A Study on the Microstructure and Mechanical Properties of Improved 25Ni-20Cr Steel via in Situ Testing
To meet the application requirements for structural components in Gen-IV nuclear reactors, it is essential to improve the high-temperature mechanical properties of 25Ni-20Cr (S35140) austenitic stainless steel. In this research, an improved austenitic stainless steel (N-S35140), derived from S35140 steel, was investigated. The scanning transmission electron microscopy (STEM) results indicate that the addition of titanium (Ti) microalloying elements to S35140 steel led to the precipitation of new strengthening nano phases, including M(C, N), MC, MN and Ti(C, N), in N-S35140. These precipitates effectively compensated for the loss of high-temperature strength resulting from the substantial reduction in carbon content. During the in situ transmission electron microscopy (TEM) compressive process at room temperature, the yield strength of N-S35140 steel is 618.4 MPa. At room temperature, the tensile strength of N-S35140 steel is 638.5 MPa, with a yield strength of 392.8 MPa and an elongation of 32.7%, which surpasses those of S35140 steel at room temperature. N-S35140 steel exhibits a tensile strength of 330.6 MPa, a yield strength of 228.2 MPa, and an elongation of 51.4% during the in situ scanning electron microscopy (SEM) tensile test conducted at 650 °C. As a consequence, the improved N-S35140 steel demonstrates significantly enhanced mechanical properties compared to the original S35140 steel, positioning it as a promising candidate for structural components in Gen-IV nuclear reactors.
- 7 March 2025
- Published by MDPI AG in Nanomaterials
- Vol. 15 (6) , 413
Open AccessA Study on the Microstructure and Mechanical Properties of Improved 25Ni-20Cr Steel via in Situ Testing
To meet the application requirements for structural components in Gen-IV nuclear reactors, it is essential to improve the high-temperature mechanical properties of 25Ni-20Cr (S35140) austenitic stainless steel. In this research, an improved austenitic stainless steel (N-S35140), derived from S35140 steel, was investigated. The scanning transmission electron microscopy (STEM) results indicate that the addition of titanium (Ti) microalloying elements to S35140 steel led to the precipitation of new strengthening nano phases, including M(C, N), MC, MN and Ti(C, N), in N-S35140. These precipitates effectively compensated for the loss of high-temperature strength resulting from the substantial reduction in carbon content. During the in situ transmission electron microscopy (TEM) compressive process at room temperature, the yield strength of N-S35140 steel is 618.4 MPa. At room temperature, the tensile strength of N-S35140 steel is 638.5 MPa, with a yield strength of 392.8 MPa and an elongation of 32.7%, which surpasses those of S35140 steel at room temperature. N-S35140 steel exhibits a tensile strength of 330.6 MPa, a yield strength of 228.2 MPa, and an elongation of 51.4% during the in situ scanning electron microscopy (SEM) tensile test conducted at 650 °C. As a consequence, the improved N-S35140 steel demonstrates significantly enhanced mechanical properties compared to the original S35140 steel, positioning it as a promising candidate for structural components in Gen-IV nuclear reactors.
- Open Access
- 20 February 2025
- Published by MDPI AG in Nanomaterials
- Vol. 15 (5) , 325
A Comprehensive Review of High Burn-Up Structure Formation in UO2: Mechanisms, Interactions, and Future Directions
In the rim zone of UO2 nuclear fuel pellets, high burn-up and low temperatures drive changes in the microstructure, leading to the formation of high burn-up structures (HBS). This review focuses on the formation of HBS, beginning with a description of the two contentious mechanisms—recrystallization and polygonization—that are believed to be the primary controlling factors. We discuss experimental and simulation studies that support both mechanisms, emphasizing that although each mechanism can explain certain aspects of HBS formation, neither recrystallization nor polygonization alone is sufficient to fully explain the observed phenomena. Furthermore, we emphasize the intrinsic relationship between these two mechanisms, suggesting that they represent different manifestations of the same underlying process under varying conditions, and we reference relevant studies that support this perspective. Lastly, we underline the significance of investigating the formation processes of HBS and provide an outlook on future research directions based on the current state of knowledge.
- 20 February 2025
- Published by MDPI AG in Nanomaterials
- Vol. 15 (5) , 325
Open AccessA Comprehensive Review of High Burn-Up Structure Formation in UO2: Mechanisms, Interactions, and Future Directions
In the rim zone of UO2 nuclear fuel pellets, high burn-up and low temperatures drive changes in the microstructure, leading to the formation of high burn-up structures (HBS). This review focuses on the formation of HBS, beginning with a description of the two contentious mechanisms—recrystallization and polygonization—that are believed to be the primary controlling factors. We discuss experimental and simulation studies that support both mechanisms, emphasizing that although each mechanism can explain certain aspects of HBS formation, neither recrystallization nor polygonization alone is sufficient to fully explain the observed phenomena. Furthermore, we emphasize the intrinsic relationship between these two mechanisms, suggesting that they represent different manifestations of the same underlying process under varying conditions, and we reference relevant studies that support this perspective. Lastly, we underline the significance of investigating the formation processes of HBS and provide an outlook on future research directions based on the current state of knowledge.
- Open Access
- 11 February 2025
- Published by Elsevier in Nuclear Engineering and Technology
- Vol. 57 (7)
Effects of high misfit on isothermal β → ω phase transformation in Ti-19V alloy: A three-dimensional phase-field simulation
- 11 February 2025
- Published by Elsevier in Nuclear Engineering and Technology
- Vol. 57 (7)
Open AccessEffects of high misfit on isothermal β → ω phase transformation in Ti-19V alloy: A three-dimensional phase-field simulation
- Open Access
- 8 February 2025
- Published by MDPI AG in Nanomaterials
- Vol. 15 (4) , 258
Study on the Corrosion Behavior of Low-Carbon 9Cr-ODS Steel in Oxygen-Saturated Lead–Bismuth Eutectic for 1000 Hours
A novel low-carbon 9Cr-ODS steel was exposed to corrosion in lead–bismuth eutectic saturated with oxygen at 500 °C for 1000 h, leading to the formation of three distinct layers of oxide film. From the outermost to the innermost layer, these included a Fe3O4 layer infiltrated with Pb, a FeCr2O4 layer, and an inner oxide zone. The inner oxide zone was primarily composed of an unoxidized matrix and Cr2O3. The formation of the inner oxide zone was primarily attributed to the preferential oxidation of Cr following the infiltration of insufficient O content. Two distinct morphologies of the inner oxide zone were identified: one is porous, while the other is non-porous. The porous morphology is characterized by low Fe content and Pb infiltration. The loss of Fe is the main factor contributing to the development of the porous inner oxide zone and the infiltration of Pb, while the short-range diffusion of Cr promotes the growth of Cr2O3, resulting in a needle-like morphology.
- 8 February 2025
- Published by MDPI AG in Nanomaterials
- Vol. 15 (4) , 258
Open AccessStudy on the Corrosion Behavior of Low-Carbon 9Cr-ODS Steel in Oxygen-Saturated Lead–Bismuth Eutectic for 1000 Hours
A novel low-carbon 9Cr-ODS steel was exposed to corrosion in lead–bismuth eutectic saturated with oxygen at 500 °C for 1000 h, leading to the formation of three distinct layers of oxide film. From the outermost to the innermost layer, these included a Fe3O4 layer infiltrated with Pb, a FeCr2O4 layer, and an inner oxide zone. The inner oxide zone was primarily composed of an unoxidized matrix and Cr2O3. The formation of the inner oxide zone was primarily attributed to the preferential oxidation of Cr following the infiltration of insufficient O content. Two distinct morphologies of the inner oxide zone were identified: one is porous, while the other is non-porous. The porous morphology is characterized by low Fe content and Pb infiltration. The loss of Fe is the main factor contributing to the development of the porous inner oxide zone and the infiltration of Pb, while the short-range diffusion of Cr promotes the growth of Cr2O3, resulting in a needle-like morphology.
- Open Access
- 13 December 2024
- Published by MDPI AG in Nanomaterials
- Vol. 14 (24) , 1999
The Impact of Laser Irradiation on Thin ZrN Films Deposited by Pulsed DC Magnetron Sputtering
Transition metal nitrides have extensive applications, including magnetic storage devices, hardware resistance coatings, and low-temperature fuel cells. This study investigated the structural, electrical, and mechanical properties of thin zirconium nitride (ZrN) films by examining the effects of laser irradiation times. Thin ZrN films were deposited on glass substrates using pulsed DC magnetron sputtering and irradiated with a diode laser for 6 and 10 min. Characterization was performed using X-ray diffraction (XRD), scanning electron microscopy (SEM), high-resolution transmission electron microscopy (HRTEM), nanoindentation, and four-point probe techniques. Extended laser irradiation times resulted in increased numbers of peaks on XRD analysis, indicating enhanced crystalline behavior of thin ZrN film. SEM analysis revealed surface voids, while HRTEM showed nanostructured ZrN with uniform plane orientation. The electrical properties of the thin ZrN film improved with extended laser irradiation, as demonstrated by a reduction in sheet resistance from 0.43 × 109 Ω to 0.04 × 109 Ω. Additionally, nanoindentation tests revealed an increase in hardness, rising from 8.91 GPa to 9.36 GPa.
- 13 December 2024
- Published by MDPI AG in Nanomaterials
- Vol. 14 (24) , 1999
Open AccessThe Impact of Laser Irradiation on Thin ZrN Films Deposited by Pulsed DC Magnetron Sputtering
Transition metal nitrides have extensive applications, including magnetic storage devices, hardware resistance coatings, and low-temperature fuel cells. This study investigated the structural, electrical, and mechanical properties of thin zirconium nitride (ZrN) films by examining the effects of laser irradiation times. Thin ZrN films were deposited on glass substrates using pulsed DC magnetron sputtering and irradiated with a diode laser for 6 and 10 min. Characterization was performed using X-ray diffraction (XRD), scanning electron microscopy (SEM), high-resolution transmission electron microscopy (HRTEM), nanoindentation, and four-point probe techniques. Extended laser irradiation times resulted in increased numbers of peaks on XRD analysis, indicating enhanced crystalline behavior of thin ZrN film. SEM analysis revealed surface voids, while HRTEM showed nanostructured ZrN with uniform plane orientation. The electrical properties of the thin ZrN film improved with extended laser irradiation, as demonstrated by a reduction in sheet resistance from 0.43 × 109 Ω to 0.04 × 109 Ω. Additionally, nanoindentation tests revealed an increase in hardness, rising from 8.91 GPa to 9.36 GPa.
- 3 December 2024
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 605
Correlation of mechanics degradation and thermal aging damage defects in Z3CN20.09M cast austenitic stainless steels
- 3 December 2024
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 605
Correlation of mechanics degradation and thermal aging damage defects in Z3CN20.09M cast austenitic stainless steels
- Open Access
Corrosion Resistance of Cr2O3, ZrO2, and Mn3O4 Oxide Films to Lead–Bismuth Eutectic: A Comparative Study
In this study, the stability of Cr2O3, ZrO2, and Mn3O4 oxide films in high-temperature liquid lead–bismuth eutectic (LBE) was systematically investigated using both experimental and first principles calculation methods. The research findings indicated that Cr2O3 demonstrated superior structural integrity at corrosion temperatures of both 600 °C and 700 °C and displayed exceptional resistance to LBE corrosion. ZrO2 demonstrates resistance to LBE infiltration. However, the emergence of cracks in the vicinity of the ZrO2 layer and the metal interface undermines the protective layer’s integrity. Mn3O4 exhibits susceptibility to corrosion by LBE and lacks resistance to its effects. First principles calculations indicate that Pb and Bi atoms are most readily adsorbed onto the Mn3O4 surface, promoting the detachment of Mn atoms. The results show that the corrosion resistance of the three oxide films is ranked in the following order: Cr2O3 > ZrO2 > Mn3O4.
Open AccessCorrosion Resistance of Cr2O3, ZrO2, and Mn3O4 Oxide Films to Lead–Bismuth Eutectic: A Comparative Study
In this study, the stability of Cr2O3, ZrO2, and Mn3O4 oxide films in high-temperature liquid lead–bismuth eutectic (LBE) was systematically investigated using both experimental and first principles calculation methods. The research findings indicated that Cr2O3 demonstrated superior structural integrity at corrosion temperatures of both 600 °C and 700 °C and displayed exceptional resistance to LBE corrosion. ZrO2 demonstrates resistance to LBE infiltration. However, the emergence of cracks in the vicinity of the ZrO2 layer and the metal interface undermines the protective layer’s integrity. Mn3O4 exhibits susceptibility to corrosion by LBE and lacks resistance to its effects. First principles calculations indicate that Pb and Bi atoms are most readily adsorbed onto the Mn3O4 surface, promoting the detachment of Mn atoms. The results show that the corrosion resistance of the three oxide films is ranked in the following order: Cr2O3 > ZrO2 > Mn3O4.