Graphite thermal expansion relationship for different temperature ranges von Tsang, D.K.L., Marsden, B.J., Fok, S.L., Hall, G.

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The microstructure of nuclear graphite binders von Wen, K.Y., Marrow, T.J., Marsden, B.J.

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Fracture behaviour of an anisotropic polygranular graphite (PGA) von Mostafavi, M., Schmidt, M.J.J., Marsden, B.J., Marrow, T.J.

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Influence of grazing and vegetation type on post-fire flammability von Kirkpatrick, J. B., Marsden-Smedley, J. B., Leonard, S. W. J.

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The development of a stress analysis code for nuclear graphite components in gas-cooled reactors von Tsang, D.K.L., Marsden, B.J.

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Changes in the coefficient of thermal expansion in stressed Gilsocarbon graphite von Preston, S.D., Marsden, B.J.

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Three-dimensional characterization and thermal property modelling of thermally oxidized nuclear graphite von Babout, L., Marsden, B.J., Mummery, P.M., Marrow, T.J.

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Numerical modelling of the effects of porosity changes on the mechanical properties of nuclear graphite von Berre, C., Fok, S.L., Marsden, B.J., Babout, L., Hodgkins, A., Marrow, T.J., Mummery, P.M.

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Microstructural modelling of nuclear graphite using multi-phase models von Berre, C., Fok, S.L., Marsden, B.J., Mummery, P.M., Marrow, T.J., Neighbour, G.B.

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The microstructural modelling of nuclear grade graphite von Hall, G., Marsden, B.J., Fok, S.L.

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4D synchrotron X-ray microtomography of fracture in nuclear graphite after neutron irradiation and radiolytic oxidation von Wade-Zhu, J., Krishna, R., Bodey, A.J., Davies, M., Bourne, N.K., Rau, C., Davies, B., Tzelepi, A., Jones, A.N., Marsden, B.J., Mummery, P.M.

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A numerical study on the application of the Weibull theory to brittle materials von Fok, S.L, Mitchell, B.C, Smart, J, Marsden, B.J

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Numerical simulation of strength test on graphite moderator bricks using a continuum damage mechanics model von Zou, Z., Fok, S.L., Marsden, B.J., Oyadiji, S.O.

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Calibration of dimensional change in finite element models using AGR moderator brick measurements von McNally, K., Hall, G., Tan, E., Marsden, B.J., Warren, N.

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Effects of dimensional change strain in nuclear graphite component stress analysis von Tsang, D.K.L., Marsden, B.J.

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Differential Stereochemical Requirements of μ vs. δ Opioid Receptors for Ligand Binding and Signal Transduction: Development of a Class of Potent and Highly δ-Selective Peptide Ant... von Schiller, Peter W., Thi M.-D. Naguyen, Weltrowska, Grazyna, Wilkes, Brian C., Marsden, Brian J., Lemieux, Carole, Chung, Nga N.

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Analyses of a restrained growth graphite irradiation creep experiment von Tsang, D.K.L., Marsden, B.J., Vreeling, J.A., van der Laan, J.

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Observation of microstructure deformation and damage in nuclear graphite von Joyce, M.R., Marrow, T.J., Mummery, P., Marsden, B.J.

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A core-monitoring based methodology for predictions of graphite weight loss in AGR moderator bricks von McNally, K., Warren, N., Fahad, M., Hall, G., Marsden, B.J.

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Origin and validity of graphite dosimetry units and related conversion factors von Black, G., Marsden, B.J., Wright, G., Jones, A.N.

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