Graphite thermal expansion relationship for different temperature ranges DKL Tsang, BJ Marsden, SL Fok, G Hall Carbon 43 (14), 2902-2906, 2005 | 229 | 2005 |
A numerical study on the application of the Weibull theory to brittle materials SL Fok, BC Mitchell, J Smart, BJ Marsden Engineering Fracture Mechanics 68 (10), 1171-1179, 2001 | 129 | 2001 |
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 | 117 | 2016 |
The microstructure of nuclear graphite binders KY Wen, TJ Marrow, BJ Marsden Carbon 46 (1), 62-71, 2008 | 116 | 2008 |
An understanding of lattice strain, defects and disorder in nuclear graphite R Krishna, J Wade, AN Jones, M Lasithiotakis, PM Mummery, BJ Marsden Carbon 124, 314-333, 2017 | 105 | 2017 |
Microcracks in nuclear graphite and highly oriented pyrolytic graphite (HOPG) K Wen, J Marrow, B Marsden Journal of Nuclear Materials 381 (1-2), 199-203, 2008 | 104 | 2008 |
Irradiation damage in graphite due to fast neutrons in fission and fusion systems BT Kelly, K Hall, BJ Marsden IAEA, 2000 | 102 | 2000 |
The development of a stress analysis code for nuclear graphite components in gas-cooled reactors DKL Tsang, BJ Marsden Journal of nuclear materials 350 (3), 208-220, 2006 | 99 | 2006 |
4.11 Graphite in Gas-Cooled Reactors BJ Marsden, GN Hall Reference Module in Materials Science and Materials Engineering, 2015 | 92 | 2015 |
Numerical modelling of the effects of porosity changes on the mechanical properties of nuclear graphite C Berre, SL Fok, BJ Marsden, L Babout, A Hodgkins, TJ Marrow, ... Journal of Nuclear Materials 352 (1-3), 1-5, 2006 | 79 | 2006 |
Fluid-tight joint with inclined flange face LV Lewis, TH Hyde, H Fessler, BJ Marsden US Patent 5,230,540, 1993 | 71 | 1993 |
X-ray tomography observation of crack propagation in nuclear graphite A Hodgkins, TJ Marrow, P Mummery, B Marsden, A Fok Materials Science and Technology 22 (9), 1045-1051, 2006 | 69 | 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 | 68 | 2008 |
The microstructural modelling of nuclear grade graphite G Hall, BJ Marsden, SL Fok Journal of nuclear materials 353 (1-2), 12-18, 2006 | 67 | 2006 |
Observation of microstructure deformation and damage in nuclear graphite MR Joyce, TJ Marrow, P Mummery, BJ Marsden Engineering Fracture Mechanics 75 (12), 3633-3645, 2008 | 58 | 2008 |
Changes in the coefficient of thermal expansion in stressed Gilsocarbon graphite SD Preston, BJ Marsden Carbon 44 (7), 1250-1257, 2006 | 57 | 2006 |
Neutron irradiation damage of nuclear graphite studied by high-resolution transmission electron microscopy and Raman spectroscopy R Krishna, AN Jones, L McDermott, BJ Marsden Journal of nuclear Materials 467, 557-565, 2015 | 55 | 2015 |
Analysis of crack propagation in nuclear graphite using three-point bending of sandwiched specimens L Shi, H Li, Z Zou, ASL Fok, BJ Marsden, A Hodgkins, PM Mummery, ... Journal of Nuclear Materials 372 (2-3), 141-151, 2008 | 52 | 2008 |
The mechanical testing of nuclear graphite BC Mitchell, J Smart, SL Fok, BJ Marsden Journal of nuclear materials 322 (2-3), 126-137, 2003 | 50 | 2003 |
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 |