| Graphite thermal expansion relationship for different temperature ranges DKL Tsang, BJ Marsden, SL Fok, G Hall Carbon 43 (14), 2902-2906, 2005 | 231 | 2005 |
| Dimensional change, irradiation creep and thermal/mechanical property changes in nuclear graphite BJ Marsden, M Haverty, W Bodel, GN Hall, AN Jones, PM Mummery, ... International Materials Reviews 61 (3), 155-182, 2016 | 122 | 2016 |
| 4.11 Graphite in Gas-Cooled Reactors BJ Marsden, GN Hall Reference Module in Materials Science and Materials Engineering, 2015 | 93 | 2015 |
| The microstructural modelling of nuclear grade graphite G Hall, BJ Marsden, SL Fok Journal of nuclear materials 353 (1-2), 12-18, 2006 | 68 | 2006 |
| Microstructural characterisation of nuclear grade graphite AN Jones, GN Hall, M Joyce, A Hodgkins, K Wen, TJ Marrow, BJ Marsden Journal of Nuclear Materials 381 (1-2), 152-157, 2008 | 67 | 2008 |
| The Osborne deposit, Cloncurry district: a 1595 Ma Cu–Au skarn deposit L Gauthier, G Hall, H Stein, U Schaltegger A hydrothermal odyssey, new developments in metalliferous hydrothermal …, 2001 | 66 | 2001 |
| Dimensional and material property changes to irradiated Gilsocarbon graphite irradiated between 650 and 750° C BJ Marsden, GN Hall, O Wouters, JA Vreeling, J Van Der Laan Journal of Nuclear Materials 381 (1-2), 62-67, 2008 | 49 | 2008 |
| Graphite as a core material for Generation IV nuclear reactors BJ Marsden, AN Jones, GN Hall, M Treifi, PM Mummery Structural materials for generation IV nuclear reactors, 495-532, 2017 | 46 | 2017 |
| Spatial variability in the coefficient of thermal expansion induces pre-service stresses in computer models of virgin Gilsocarbon bricks JD Arregui-Mena, L Margetts, DV Griffiths, L Lever, G Hall, PM Mummery Journal of Nuclear Materials 465, 793-804, 2015 | 25 | 2015 |
| A review of finite element method models for nuclear graphite applications JD Arregui-Mena, RN Worth, G Hall, PD Edmondson, AB Giorla, ... Archives of Computational Methods in Engineering 27, 331-350, 2020 | 24 | 2020 |
| The relationship between irradiation induced dimensional change and the coefficient of thermal expansion: a modified Simmons relationship G Hall, BJ Marsden, SL Fok, J Smart Nuclear engineering and design 222 (2-3), 319-330, 2003 | 24 | 2003 |
| A model of Young's modulus for Gilsocarbon graphites irradiated in oxidising environments E Eason, G Hall, G Marsden, Barry, Heys Journal of Nuclear Materials 436 (1), 201-207, 2013 | 19 | 2013 |
| Models of bending strength for gilsocarbon graphites irradiated in inert and oxidising environments E Eason, G Hall, G Marsden, Barry, Heys Journal of Nuclear Materials 436 (1), 208-216, 2013 | 18 | 2013 |
| Development of a Model of Dimensional Change in AGR Graphites Irradiated in Inert Environments ED Eason, GN Hall, BJ Marsden SPECIAL PUBLICATION-ROYAL SOCIETY OF CHEMISTRY 309, 43, 2007 | 16 | 2007 |
| Calibration of dimensional change in finite element models using AGR moderator brick measurements K McNally, G Hall, E Tan, BJ Marsden, N Warren Journal of Nuclear Materials 451 (1-3), 179-188, 2014 | 14 | 2014 |
| Comprehensive Nuclear Materials, vol. 4 BJ Marsden, GN Hall Elsevier, 2012 | 14 | 2012 |
| Development of a Young's modulus model for Gilsocarbon graphites irradiated in inert environments ED Eason, GN Hall, BJ Marsden, GB Heys Journal of Nuclear Materials 381 (1-2), 145-151, 2008 | 13 | 2008 |
| A numerical study of internal brick stresses in AGR moderator bricks K McNally, M Fahad, E Tan, N Warren, GN Hall, BJ Marsden Nuclear Engineering and Design 309, 277-293, 2016 | 10 | 2016 |
| Models of coefficient of thermal expansion (cte) for gilsocarbon graphites irradiated in inert and oxidising environments E Eason, G Hall, G Marsden, Barry, Heys Journal of Nuclear Materials 436 (1), 191-200, 2013 | 10 | 2013 |
| Investigating the effects of stress on the pore structures of nuclear grade graphites JEL Taylor, GN Hall, PM Mummery Journal of Nuclear Materials 470, 216-228, 2016 | 9 | 2016 |
