Yiqiang Wang
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Previous Organizations / Institutes
The organizations / institutes from the scholar's other articles in the past ten years
Yiqiang Wang has a total of 117 co-authors. Here are the top co-authors by number of shared publications:
- Biao Cai
School of Metallurgy and Materials University of Birmingham Birmingham B15 2TT UK
5 shared publications - Bo Chen
School of Engineering, University of Leicester, Leicester, UK
5 shared publications D.J. Smith
4 shared publications- Peter David Lee
Department of Mechanical Engineering, University College London, London, UK
4 shared publications D. J. Smith
Department of Mechanical Engineering, University of Bristol, Bristol BS8 1TR, United Kingdom
3 shared publications- Kun Yan
Department of Materials, The University of Manchester, Manchester, UK
3 shared publications
Latest Publications
- 3 July 2025
- Published by The Royal Society in Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences
- Vol. 383 (2300) , 20240180
Ensuring the structural integrity of tokamak fusion power plants: challenges, progress and pathway
Structural integrity for fusion is an integrated multi-disciplinary subject spanning the science of materials, technology, engineering, health monitoring and simulation methods and algorithms for scrutinizing the assurance of reliable fusion reactor performance from the whole plant design phase through operation to decommissioning. Structural integrity is essential for maintaining high standards of public, environmental and investment protection and maximizing economic benefits. While fusion shares many of the structural integrity challenges faced by other industries, it also presents unique complexities. These include distinct regulatory requirements compared with fission, the need for innovative materials suited to extreme environments, advanced manufacturing techniques for component fabrication and the establishment of new facilities for technology demonstration, design verification and validation. Additionally, developing qualification processes, design rules, lifetime assessment methods, procedures, codes and standards is essential for verifying fusion reactor designs and predicting the lifespan of systems, structures and components. This paper reviews the challenges and advancements in fusion structural integrity, focusing on the tokamak concept and key in-vessel components: the breeding blanket and the divertor. It covers fusion regulations, operational environments, load cases, multi-material joints and the creation of fusion-specific design criteria. The paper concludes with a recommended pathway for future research, development and collaboration to advance commercial fusion energy. This article is part of the theme issue ‘Future challenges for structural integrity of high-integrity components’.
- 3 July 2025
- Published by The Royal Society in Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences
- Vol. 383 (2300) , 20240180
Ensuring the structural integrity of tokamak fusion power plants: challenges, progress and pathway
Structural integrity for fusion is an integrated multi-disciplinary subject spanning the science of materials, technology, engineering, health monitoring and simulation methods and algorithms for scrutinizing the assurance of reliable fusion reactor performance from the whole plant design phase through operation to decommissioning. Structural integrity is essential for maintaining high standards of public, environmental and investment protection and maximizing economic benefits. While fusion shares many of the structural integrity challenges faced by other industries, it also presents unique complexities. These include distinct regulatory requirements compared with fission, the need for innovative materials suited to extreme environments, advanced manufacturing techniques for component fabrication and the establishment of new facilities for technology demonstration, design verification and validation. Additionally, developing qualification processes, design rules, lifetime assessment methods, procedures, codes and standards is essential for verifying fusion reactor designs and predicting the lifespan of systems, structures and components. This paper reviews the challenges and advancements in fusion structural integrity, focusing on the tokamak concept and key in-vessel components: the breeding blanket and the divertor. It covers fusion regulations, operational environments, load cases, multi-material joints and the creation of fusion-specific design criteria. The paper concludes with a recommended pathway for future research, development and collaboration to advance commercial fusion energy. This article is part of the theme issue ‘Future challenges for structural integrity of high-integrity components’.
- Open Access
- 4 April 2024
- Published by Elsevier in Acta Materialia
- Vol. 271
In-Situ synchrotron investigation of elastic and tensile properties of oxide dispersion strengthened EUROFER97 steel for advanced fusion reactors
- 4 April 2024
- Published by Elsevier in Acta Materialia
- Vol. 271
Open AccessIn-Situ synchrotron investigation of elastic and tensile properties of oxide dispersion strengthened EUROFER97 steel for advanced fusion reactors
- Open Access
- 16 March 2024
- Published by Elsevier in Acta Materialia
- Vol. 270
Insights into primary carbides and nanoparticles in an additively manufactured high-alloy steel
- 16 March 2024
- Published by Elsevier in Acta Materialia
- Vol. 270
Open AccessInsights into primary carbides and nanoparticles in an additively manufactured high-alloy steel
- Open Access
- 20 January 2024
- Published by Elsevier in Nuclear Materials and Energy
- Vol. 38
The use of time-of-flight neutron Bragg edge imaging to measure the residual strains in W/Cu dissimilar joints for fusion reactors
- 20 January 2024
- Published by Elsevier in Nuclear Materials and Energy
- Vol. 38
Open AccessThe use of time-of-flight neutron Bragg edge imaging to measure the residual strains in W/Cu dissimilar joints for fusion reactors
- Open Access
- 15 June 2023
- Published by Elsevier in Nuclear Materials and Energy
- Vol. 36
Neutron Bragg edge tomography characterisation of residual strain in a laser-welded Eurofer97 joint
- 15 June 2023
- Published by Elsevier in Nuclear Materials and Energy
- Vol. 36
Open AccessNeutron Bragg edge tomography characterisation of residual strain in a laser-welded Eurofer97 joint
- 9 July 2022
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 569
Mechanical characterisation of V-4Cr-4Ti alloy: Tensile tests under high energy synchrotron diffraction
- 9 July 2022
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 569
Mechanical characterisation of V-4Cr-4Ti alloy: Tensile tests under high energy synchrotron diffraction
- Open Access
- 1 September 2021
- Published by IOP Publishing in Journal of Physics: Conference Series
- Vol. 2037 (1) , 012062
Multi-objective Optimization of High Speed Milling Parameters Based on Genetic Algorithm
In order to optimize the high-speed milling parameters and reduce the experimental work in the actual processing, a multi-objective optimization model is established. The improved genetic algorithm NSGA-II combined with penalty function method is used to solve the mathematical model, and the optimal cutting parameters are obtained when the high-speed milling conditions are known, which provides guidance for the process decision-making of high-speed milling.
- 1 September 2021
- Published by IOP Publishing in Journal of Physics: Conference Series
- Vol. 2037 (1) , 012062
Open AccessMulti-objective Optimization of High Speed Milling Parameters Based on Genetic Algorithm
In order to optimize the high-speed milling parameters and reduce the experimental work in the actual processing, a multi-objective optimization model is established. The improved genetic algorithm NSGA-II combined with penalty function method is used to solve the mathematical model, and the optimal cutting parameters are obtained when the high-speed milling conditions are known, which provides guidance for the process decision-making of high-speed milling.
- 1 October 2020
- Published by Elsevier in Computational Materials Science
- Vol. 183
Microstructure-informed, predictive crystal plasticity finite element model of fatigue-dwells
- 1 October 2020
- Published by Elsevier in Computational Materials Science
- Vol. 183
Microstructure-informed, predictive crystal plasticity finite element model of fatigue-dwells
- 1 March 2020
- Published by Elsevier in Scripta Materialia
- Vol. 178, 166-170
Deformation mechanisms of FeCoCrNiMo0.2 high entropy alloy at 77 and 15 K
- 1 March 2020
- Published by Elsevier in Scripta Materialia
- Vol. 178, 166-170
Deformation mechanisms of FeCoCrNiMo0.2 high entropy alloy at 77 and 15 K
- Open Access
Laser Powder Bed Fusion of Precipitation-Hardened Martensitic Stainless Steels: A Review
Martensitic stainless steels are widely used in industries due to their high strength and good corrosion resistance performance. Precipitation-hardened (PH) martensitic stainless steels feature very high strength compared with other stainless steels, around 3-4 times the strength of austenitic stainless steels such as 304 and 316. However, the poor workability due to the high strength and hardness induced by precipitation hardening limits the extensive utilization of PH stainless steels as structural components of complex shapes. Laser powder bed fusion (L-PBF) is an attractive additive manufacturing technology, which not only exhibits the advantages of producing complex and precise parts with a short lead time, but also avoids or reduces the subsequent machining process. In this review, the microstructures of martensitic stainless steels in the as-built state, as well as the effects of process parameters, building atmosphere, and heat treatments on the microstructures, are reviewed. Then, the characteristics of defects in the as-built state and the causes are specifically analyzed. Afterward, the effect of process parameters and heat treatment conditions on mechanical properties are summarized and reviewed. Finally, the remaining issues and suggestions on future research on L-PBF of martensitic precipitation-hardened stainless steels are put forward.
Open AccessLaser Powder Bed Fusion of Precipitation-Hardened Martensitic Stainless Steels: A Review
Martensitic stainless steels are widely used in industries due to their high strength and good corrosion resistance performance. Precipitation-hardened (PH) martensitic stainless steels feature very high strength compared with other stainless steels, around 3-4 times the strength of austenitic stainless steels such as 304 and 316. However, the poor workability due to the high strength and hardness induced by precipitation hardening limits the extensive utilization of PH stainless steels as structural components of complex shapes. Laser powder bed fusion (L-PBF) is an attractive additive manufacturing technology, which not only exhibits the advantages of producing complex and precise parts with a short lead time, but also avoids or reduces the subsequent machining process. In this review, the microstructures of martensitic stainless steels in the as-built state, as well as the effects of process parameters, building atmosphere, and heat treatments on the microstructures, are reviewed. Then, the characteristics of defects in the as-built state and the causes are specifically analyzed. Afterward, the effect of process parameters and heat treatment conditions on mechanical properties are summarized and reviewed. Finally, the remaining issues and suggestions on future research on L-PBF of martensitic precipitation-hardened stainless steels are put forward.