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Dr Graham Hall (EngD) - publications

List of publications

Unknown

2012

  • 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