Marsden B, , Hall G. Graphite: a UK perspective. Comprehensive Nuclear Materials. Elsevier.2012: eScholarID:184676
2010
Eason, E D; Hall, G; Marsden, B J; Heys, G B. Models of coefficient of thermal expansion (CTE) for Gisocarbon graphites irradiated in inert and oxidising environments. 2010: -. eScholarID:153497
Hall G, , Marsden B, , Jones A. Graphite for nuclear reactors. Transactions of the American Nuclear Society. 2010; 102: 721-722. eScholarID:184677
2008
Wang, H T; Hall, G; Yu, S Y; Yao, Z H. Numerical Simulation of Graphite Properties Using X-ray Tomography and Fast Multipole Boundary Element Method. Computer Modelling in Engineering & Sciences. 2008; 37(2): 153-174. eScholarID:153495 | DOI:10.3970/cmes.2008.037.153
Berre, C, Graham Hall, Barry Marsden, S L Fok, T J Marrow, and P M Mummery. Modelling of Nuclear Grade Graphite Using X-Ray Tomography Data. SMINS, OECD(NE), In co-operation with the IAEA, Karlsruhe, Germany. 2008: eScholarID:2e990
Eason E, Hall G, Marsden B, Heys G. Development of a Youngs modulus model for Gilsocarbon graphites irradiated in inert environments. Journal of Nuclear Materials. 2008 October; 381(1-2): 145-151. eScholarID:1e763 | DOI:10.1016/j.jnucmat.2008.07.036
Eason E, Hall G, Heys G, Knott J, Marsden B, Preston S, Swan T. The origins and use of the equivalent temperature concept. Journal of Nuclear Materials. 2008 October; 381(1-2): 106-113. eScholarID:1e761 | DOI:10.1016/j.jnucmat.2008.07.016
Hall, Graham, D James, Abbie Jones, T J Marrow, Barry Marsden, P M Mummery, and K Wen. Characterisation and Modelling of Microstructure Heterogeneity in Nuclear Graphite. INGSM-9, Netherlands. 2008: eScholarID:2e983
James, D, Graham Hall, Abbie Jones, T J Marrow, Barry Marsden, P M Mummery, and K Wen. Characterisation and modelling of microstructure heterogeneity in nuclear graphite. Securing the Safe Performance of Graphite Reactor Cores, Nottingham. 2008: -. eScholarID:2e998
Jones, Abbie, Graham Hall, L McDermott, Barry Marsden, and T J Marrow. Characterisation of Irradiated Nuclear Graphite. INGSM-9, Netherlands. 2008: eScholarID:2e982
Jones A, Hall G, Joyce M, Hodgkins A, Wen K, Marrow T, Marsden B. Microstructural characterisation of nuclear grade graphite. Journal of Nuclear Materials. 2008 October; 381(1-2): 152-157. eScholarID:1e764 | DOI:10.1016/j.jnucmat.2008.07.038
Marsden, Barry, Abbie Jones, T J Marrow, Graham Hall, D James, and K Wen. Characterisation and Modelling of Microstructure Heterogeneity in nuclear Graphite. 7th EPRI International Decommissioning and Radioactive Waste Workshop (in collaboration with EDT-CIDEN), Lyon. 2008: eScholarID:2e980
Marsden B, Hall G, Wouters O, Vreeling J, van der Laan J. Dimensional and material property changes to irradiated Gilsocarbon graphite irradiated between 650 and 750 C. Journal of Nuclear Materials. 2008 October; 381(1-2): 62-67. eScholarID:1e759 | DOI:10.1016/j.jnucmat.2008.07.018
Sumita, J, T Shibata, E Kunimoto, K Sawa, Graham Hall, and Barry Marsden. The development of a microstructural model to evaluate the irradiation-induced property changes in IG-110 graphite using x-ray tomography. Securing the Safe Performance of Graphite Reactor Cores, Nottingham. 2008: -. eScholarID:2e999
2007
Hall, Graham, Barry Marsden, Abbie Jones, and D James. X-ray tomography of irradiated graphite. INGSM-8, Bakubung, South Africa. 2007: eScholarID:2e987
2006
Hall, Graham, Barry Marsden, J A Vreeling, and J Laan. Possibilities for the Microstructural Modelling of the Irradiation Properties of Graphites for Future High Temperature Reactors. HTR-2006, South Africa. 2006: eScholarID:2e721
Hall G, Marsden B, Fok S. The microstructural modelling of nuclear grade graphite. Journal of Nuclear Materials. 2006; 353: 12-18. eScholarID:1e549 | DOI:10.1016/j.jnucmat.2006.02.082
Jones, Abbie, Barry Marsden, Keyun Wen, Graham Hall, T J Marrow, A Hodgkins, and M Joyce. Microstructural Characterisation of Nuclear Grade Graphite. 7th International Nuclear Graphite Specialists Meeting (INGSM-7), ORNL. 2006: eScholarID:2e829
2005
Tsang, D K L; Marsden, B J; Fok, S L; Hall, G. Graphite thermal expansion relationship for different temperature ranges. Carbon. 2005; 43: 2902-2906. eScholarID:153494 | DOI:10.1016/j.carbon.2005.06.009
Eason, E D, Graham Hall, and Barry Marsden. Development of a model of dimensional change in AGR graphites irradiated in inert environments. Ageing Management of Graphite Reactor Cores, Wales. 2005: eScholarID:2e811
Hall, Graham, C Berre, Barry Marsden, and A S Fok. Microstructural modelling. IAEA Technical Working Group on Gas-Cooled Reactors, Manchester. 2005: eScholarID:2e809
Hall, Graham, Barry Marsden, Keyun Wen, C Berre, L Babout, and A Hodgkins. Ongoing microstructural studies at the University of Manchester. 6th International Nuclear Graphite Specialists Meeting (INGSM-6), France. 2005: eScholarID:2e810
Marsden, Barry, Graham Hall, and A S Fok. Descriptions and summary of national programmes in gas-cooled reactors - United Kingdom. IAEA Technical Working Group on Gas-Cooled Reactors, Manchester. 2005: eScholarID:2e808
Tsang D, Marsden B, Fok S, Hall G. Graphite thermal expansion relationship for different temperature ranges. Carbon. 2005; 43: 2902-2906. eScholarID:184678
2004
Hall, Graham, and Barry Marsden. Methods for the prediction of graphite irradiation dimensional and property changes in pressure tube reactor graphite. International Conference on Pressure Tube Reactors: Problems and Solutions, Russia. 2004: eScholarID:2e812
2003
Hall, Graham, and Barry Marsden. Microstructural modelling of nuclear grade graphite. Universities Nuclear Technology Forum, Enlgand. 2003: -. eScholarID:2e813
Hall, Graham, Barry Marsden, and S L Fok. The microstructural modelling of nuclear grade graphite. 4th International Nuclear Graphite Specialists Meeting (INGSM-4), Japan. 2003: eScholarID:2e816
Hall G, Marsden B, Fok S, Smart J. The relationship between irradiation induced dimensional change and the coefficient of thermal expansion: A modified Simmons relationship. Nuclear Engineering and Design . 2003; 222: 319-330. eScholarID:1e552 | DOI:10.1016/S0029-5493(03)00035-9
Marsden, Barry, S L Fok, and Graham Hall. Comparison of UK, American and Japanese unirradiated graphite CTE methodologies. 18th Technical Working Group on Gas Cooled Reactors (TWG-GCR-18), Turkey. 2003: eScholarID:2e817
Marsden, Barry, S L Fok, and Graham Hall. Descriptions and summary of national programmes in gas-cooled reactors - United Kingdom. 18th Technical Working Group on Gas Cooled Reactors (TWG-GCR-18), Turkey. 2003: eScholarID:2e818
Marsden, Barry, S L Fok, and Graham Hall. High temperature gas-cooled reactor core design future material consideration. International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP2003), Japan. 2003: eScholarID:2e814
2002
Hall G, Marsden B, Smart J, Fok A. Finite-element modelling of nuclear grade graphite. Nuclear Energy. 2002; 41: 53-62. eScholarID:1e539 | DOI:10.1680/nuen.41.1.53.39011
Hall, Graham, Barry Marsden, A Fok, and J Smart. The relationship between irradiation induced dimensional change and the coefficient of thermal expansion: A new look. Conference on High Temperature Reactors (HTR-2002), the Netherlands. 2002: eScholarID:2e819
