Barry Marsden
About
In The Last Decade
Barry Marsden
107 papers receiving 1.7k citations
Peers
Comparison fields: 5 of 86
- Materials Chemistry 1.5k
- Safety, Risk, Reliability and Quality 826
- Mechanics of Materials 308
- Mechanical Engineering 260
- Aerospace Engineering 216
Countries citing papers authored by Barry Marsden
This map shows the geographic impact of Barry Marsden's research. It shows the number of citations coming from papers published by authors working in each country. You can also color the map by specialization and compare the number of citations received by Barry Marsden with the expected number of citations based on a country's size and research output (numbers larger than one mean the country cites Barry Marsden more than expected).
Fields of papers citing papers by Barry Marsden
This network shows the impact of papers produced by Barry Marsden. Nodes represent research fields, and links connect fields that are likely to share authors. Colored nodes show fields that tend to cite the papers produced by Barry Marsden. The network helps show where Barry Marsden may publish in the future.
Co-authorship network of co-authors of Barry Marsden
This figure shows the co-authorship network connecting the top 25 collaborators of Barry Marsden. A scholar is included among the top collaborators of Barry Marsden based on the total number of citations received by their joint publications. Widths of edges represent the number of papers authors have co-authored together. Node borders signify the number of papers an author published with Barry Marsden. Barry Marsden is excluded from the visualization to improve readability, since they are connected to all nodes in the network.
All Works
| # | Work | Indexed citations |
|---|---|---|
| 1 | 0 | |
| 2 | 8 | |
| 3 | 24 | |
| 4 | 10 | |
| 5 | A mathematical stress analysis model for isotropic nuclear graphite under irradiation condition | 5 |
| 6 | Failure Analysis of the Effects of Porosity in Thermally Oxidised Nuclear Graphite Using Finite Element Modelling | 1 |
| 7 | 29 | |
| 8 | The development of a microstructural model to evaluate the irradiation-induced property changes in IG-110 graphite using x-ray tomography | 3 |
| 9 | 43 | |
| 10 | 47 | |
| 11 | Constitutive Material Model for the Prediction of Stresses in Irradiated Anisotropic Graphite Components | 1 |
| 12 | A simple mathematical model for isotropic nuclear graphite under irradiation condition | 2 |
| 13 | X-Ray Tomographic Observations Applied to Porosity Models for the Thermal Properties of Oxidised Nuclear Graphite | 1 |
| 14 | 22 | |
| 15 | 12 | |
| 16 | 4 | |
| 17 | 1 | |
| 18 | Irradiation Damage in Graphite due to Fast Neutrons in Fission and Fusion Systems | 59 |
| 19 | A probabilistic approach to assessing AGR core life | 5 |
| 20 | 2 |
Rankless uses publication and citation data sourced from OpenAlex, an open and comprehensive bibliographic database. While OpenAlex provides broad and valuable coverage of the global research landscape, it—like all bibliographic datasets—has inherent limitations. These include incomplete records, variations in author disambiguation, differences in journal indexing, and delays in data updates. As a result, some metrics and network relationships displayed in Rankless may not fully capture the entirety of a scholar's output or impact.