Mark R Wenman

Mark R Wenman

Imperial College London

H-index: 24

Europe-United Kingdom

About Mark R Wenman

Mark R Wenman, With an exceptional h-index of 24 and a recent h-index of 22 (since 2020), a distinguished researcher at Imperial College London, specializes in the field of Nuclear materials, steels, zirconium alloys, modelling, corrosion.

His recent articles reflect a diverse array of research interests and contributions to the field:

Testing Outlier Detection Algorithms for Identifying Early-Stage Solute Clusters in Atom Probe Tomography

Hydrogen concentration and hydrides in Zircaloy-4 during cyclic thermomechanical loading (Vol 221, 117368, 2021)

Corrosion of 316 L exposed to highly concentrated borated water used as shield in nuclear fusion experimental reactors cooling circuits

Adapting U-Net for linear elastic stress estimation in polycrystal Zr microstructures

Corrigendum to Hydrogen concentration and hydrides in Zircaloy-4 during cyclic thermomechanical loading Volume 221, December 2021, 117368

Residual stresses in as-manufactured TRISO Coated Particle Fuel (CPF)

Transferability of Zr-Zr interatomic potentials

Peridynamic modelling of cracking in TRISO particles for high temperature reactors

Mark R Wenman Information

University

Position

___

Citations(all)

1552

Citations(since 2020)

1134

Cited By

815

hIndex(all)

24

hIndex(since 2020)

22

i10Index(all)

43

i10Index(since 2020)

38

Email

University Profile Page

Google Scholar

Mark R Wenman Skills & Research Interests

Nuclear materials

steels

zirconium alloys

modelling

corrosion

Top articles of Mark R Wenman

Testing Outlier Detection Algorithms for Identifying Early-Stage Solute Clusters in Atom Probe Tomography

arXiv preprint arXiv:2402.13734

2024/2/21

Hydrogen concentration and hydrides in Zircaloy-4 during cyclic thermomechanical loading (Vol 221, 117368, 2021)

Acta Materialia

2021/12/1

Yang Liu
Yang Liu

H-Index: 18

Mark R Wenman
Mark R Wenman

H-Index: 18

Corrosion of 316 L exposed to highly concentrated borated water used as shield in nuclear fusion experimental reactors cooling circuits

Corrosion Science

2024/2/8

Adapting U-Net for linear elastic stress estimation in polycrystal Zr microstructures

Mechanics of Materials

2024/2/7

Corrigendum to Hydrogen concentration and hydrides in Zircaloy-4 during cyclic thermomechanical loading Volume 221, December 2021, 117368

Acta Materialia

2024/2

Yang Liu
Yang Liu

H-Index: 18

Mark R Wenman
Mark R Wenman

H-Index: 18

Residual stresses in as-manufactured TRISO Coated Particle Fuel (CPF)

Journal of Nuclear Materials

2023/12/1

Daniel Shepherd
Daniel Shepherd

H-Index: 24

Mark R Wenman
Mark R Wenman

H-Index: 18

Transferability of Zr-Zr interatomic potentials

Journal of Nuclear Materials

2023/10/1

Jana Smutna
Jana Smutna

H-Index: 1

Mark R Wenman
Mark R Wenman

H-Index: 18

Peridynamic modelling of cracking in TRISO particles for high temperature reactors

Journal of Nuclear Materials

2023/4/1

Thermal expansion and steam oxidation of uranium mononitride analysed via in situ neutron diffraction

Journal of Nuclear Materials

2023/3/1

Mark R Wenman
Mark R Wenman

H-Index: 18

The bonding of H in Zr under strain

Journal of Nuclear Materials

2023/1/1

Dislocation modelling of the plastic relaxation and thermal ratchetting induced by zirconium hydride precipitation

Journal of the Mechanics and Physics of Solids

2022/10/1

Atomic scale simulation of the strain rate and temperature dependence of crack growth and stacking faults in zirconium

Computational Materials Science

2022/4/15

High temperature zirconium alloys for fusion energy

2022/2/1

On the influence of microstructure on the neutron irradiation response of HIPed SA508 steel for nuclear applications

Journal of Nuclear Materials

2022/2/1

Mark R Wenman
Mark R Wenman

H-Index: 18

Atomistic modelling of iodine-oxygen interactions in strained sub-oxides of zirconium

Journal of Nuclear Materials

2022/1/1

Discrete dislocation modelling of δ hydrides in Zr: towards an understanding of the importance of interfacial stresses for crack initiation

Journal of Nuclear Materials

2022/12/15

Application of Weibull fracture strength distributions to modelling crack initiation behaviour in nuclear fuel pellets using peridynamics

Journal of Nuclear Materials

2022/12/15

The accommodation of lithium in bulk ZrO2

Solid State Ionics

2021/12/15

Mark R Wenman
Mark R Wenman

H-Index: 18

Plastic relaxation and solute segregation to β-Nb second phase particles in Zr-Nb alloys: A discrete dislocation plasticity study

Journal of the Mechanics and Physics of Solids

2021/11/1

Nanoscale characterisation of hydrides and secondary phase particles in Zircaloy-4

arXiv preprint arXiv:2109.10955

2021/9/22

See List of Professors in Mark R Wenman University(Imperial College London)