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Dr Graham Hall (EngD) - publications

List of publications

2016

2015

  • Treifi, M., Marsden, B., Hall, G., & Mummery, P. (2015). A Strain Energy Approach for Predicting Keyway Root Cracking of an AGR Graphite Brick. In host publication.. Publication link: 4f866cc0-9dd7-43dc-98b3-22b1f95dcb3a
  • Arregui Mena, J., Margetts, L., Griffiths, D. V., Lever, L., Hall, G., & Mummery, P. (2015). Spatial variability in the coefficient of thermal expansion induces pre-service stresses in computer models of virgin Gilsocarbon bricks. Journal of Nuclear Materials, 465, 793-804. DOI:http://dx.doi.org/10.1016/j.jnucmat.2015.05.058. Publication link: 0bf4b092-8e15-461c-901a-40a121e0b369
  • Margetts, L., Arregui-Mena, J., Hall, G., Lever, L., Griffiths, D. V., & Mummery, P. (2015). Two tier parallel computation for stochastic thermo-mechanical modelling of nuclear graphite reactor cores. In host publication.. Publication link: 95d4e2e7-f16d-422b-9524-52b6ebf3c9f7

2014

  • McNally, K., Hall, G., Tan, E., Marsden, B. J., & Warren, N. (2014). Calibration of dimensional change in finite element models using AGR moderator brick measurements. Journal of Nuclear Materials, 451(1-3), 179-188. DOI:10.1016/j.jnucmat.2014.03.015. Publication link: 49288bf4-461b-4502-9b73-addbdd8b5e76
  • Arregui-Mena, J. D., Margetts, L., Lever, L., Hall, G., & Mummery, P. (2014). Stochastic thermomechanical analysis of nuclear graphite using ParaFEM. In host publication.. Publication link: d35d2112-9caa-4714-90d4-89d4173686e5
  • Treifi, M., Marsden, B., Hall, G., & Mummery, P. (2014). On the modelling and simulation of a nuclear graphite brick: effects of cracks and interactions. In host publication.. Publication link: d3d47965-b702-4d65-abf3-b1ae55ba01fe
  • Arregui-Mena, J. D., Margetts, L., Griffiths, D. V., Lever, L., Hall, G. N., & Mummery, P. (2014). Studies of the material properties of nuclear graphite using the random finite element method. In host publication.. Publication link: ef40def6-afdc-4224-9c16-aa93a632e75f

2013

  • Eason, E. D., Hall, G. N., Marsden, B. J., & Heys, G. B. (2013). Models of bending strength for Gilsocarbon graphites irradiated in inert and oxidising environments. Journal of Nuclear Materials, 436(1-3), 208-216. DOI:10.1016/j.jnucmat.2012.06.034. Publication link: 8edc23e6-d646-44fc-921a-5da8e34522a0
  • Eason, E. D., Hall, G. N., Marsden, B. J., & Heys, G. B. (2013). Models of coefficient of thermal expansion (CTE) for Gilsocarbon graphites irradiated in inert and oxidising environments. Journal of Nuclear Materials, 436(1-3), 191-200. DOI:10.1016/j.jnucmat.2012.08.022. Publication link: 356eb6f8-bfd1-4364-8661-a1fbb8e41b9c
  • Eason, E. D., Hall, G. N., Marsden, B. J., & Heys, G. B. (2013). A Model of Youngs Modulus for Gilsocarbon Graphites Irradiated in Oxidising Environments. Journal of Nuclear Materials, 436(1-3), 201-207. DOI:10.1016/j.jnucmat.2012.06.035. Publication link: 1ecde160-80f0-4d30-84be-b384cf5dbf86
  • Eason, E. D., Hall, G. N., Marsden, B. J., & Heys, G. B. (2013). A model of Young's modulus for Gilsocarbon graphites irradiated in oxidising environments. Journal of Nuclear Materials, 436(1), 201-207. . Publication link: 16f64a6d-e564-457e-85b9-96e4a8aeb5e4

2012

  • Marsden, B. J., Hall, G., & Konings, R. J. M. (Ed.) (2012). Graphite: a UK perspective. In Comprehensive Nuclear Materials. (pp. 325-390). Elsevier. . Publication link: 88a4b5e5-90c0-4a0e-b978-29c9f11b115e
  • Bowen, P., Hall, G., Poulter, L., Lamb, M., & Marsden, B. J. (2012). The UK Graphite Technical Advisory Committee for nuclear plant. In host publication.. Publication link: d1323931-411e-49c0-86ed-5a450ddc0026

2011

  • Bakenne, A. T., Mecklenburgh, J., Marsden, B., Jones, A., & Hall, G. (2011). High-pressure measurement of the mechanical properties of nuclear graphite. In host publication.. Publication link: 5ce06e41-2b17-4629-8c3b-f2e2d1805169
  • Luyken, L., Stringer, R. M., Benyezzar, M., Schmidt, M., Lowe, T., Jones, A., ... Marsden, B. (2011). The effect of bromination on the dimensional change and modulus of nuclear graphites. In host publication.. Publication link: 12a38275-8d3f-4247-9f58-2b8211afa3a1
  • Hall, G., McNally, K., Marsden, B. J., & Warren, N. (2011). Estimation of graphite dimensional changes due to combined fast neutron irradiation and radiolytic oxidation. In host publication.. Publication link: 35dd5fe8-6f08-4a51-82bc-ebfd007bde1f
  • Hall, G., McNally, K., Marsden, B. J., & Warren, N. (2011). Approximation of graphite dimensional changes in an oxidising environment. In host publication.. Publication link: 2f4a1b21-e263-4e78-8e1b-fb583c6e8dac
  • McNally, K., Hall, G., Tan, E., Warren, N., & Marsden, B. J. (2011). Calibration of a physical model for AGR moderator bricks using channel geometry measurements. In host publication.. Publication link: 2f0c41c6-3b7f-476a-b771-f26b413cf1c7

2010

  • Hall, G., Eason, E. D., Marsden, B. J., & Heys, G. B. (2010). Models of coefficient of thermal expansion (CTE) for Gisocarbon graphites irradiated in inert and oxidising environments. In host publication.. Publication link: ff497f84-089c-4114-9889-89ba35cddef5
  • Hall, G., Marsden, B. J., & Jones, A. (2010). Graphite for Nuclear Reactors. Transactions of the American Nuclear Society, 102, 721-722. . Publication link: 5320900d-ce98-4a0b-9dc0-f2ee4d9f5b2f

2009

  • Hall, G., Marsden, B., Jones, A., & Bekenne, T. (2009). Characterisation of Irradiated Graphite: NBG-10 and PCEA. In Characterisation of Irradiated Graphite: NBG-10 and PCEA.. Publication link: 7b0e86ba-8b96-432e-93ed-1b7ec8406b08

2008

  • Marsden, B., Hall, G., Vreeling, J. A., Laan, J. V. D., & Wouters, O. (2008). Dimensional and material property changes to irradiated Gilsocarbon graphite irradiated between 650 and 750 C. Journal of Nuclear Materials, 381(0), 62-67. . Publication link: d7e01b04-6828-4455-b800-36b911f9eedb
  • Marsden, B., Jones, A., Marrow, T. J., Hall, G., James, D., & Wen, K. (2008). Characterisation and Modelling of Microstructure Heterogeneity in Nuclear Graphite. In 7th EPRI International Decommissioning and Radioactive Waste Workshop (in collaboration with EDT-CIDEN), Lyon.. Publication link: dcd8314a-3741-4053-b6ed-e4a3003850e0
  • James, D., Hall, G., Jones, A., Marrow, T. J., Marsden, B., Mummery, P., & Wen, K. (2008). Characterisation and modelling of microstructure heterogeneity in nuclear graphite. In Securing the Safe Performance of Graphite Reactor Cores, Nottingham.. Publication link: f30fd119-e7ad-4832-83ca-5dbe443bbf5c
  • Jones, A., Hall, G., McDermott, L., Marsden, B., & Marrow, T. J. (2008). Characterisation of Irradiated Nuclear Graphite. In INGSM-9, Netherlands.. Publication link: 38e24ad3-4b29-45f2-ba8d-d00981e296a2
  • Sumita, J., Shibata, T., Kunimoto, E., Sawa, K., Hall, G., & Marsden, B. (2008). The development of a microstructural model to evaluate the irradiation-induced property changes in IG-110 graphite using x-ray tomography. In Securing the Safe Performance of Graphite Reactor Cores, Nottingham.. Publication link: 387457df-94c0-49c6-a5fd-9f90605b1d6b
  • Hall, G., James, D., Jones, A., Marrow, T. J., Marsden, B., Mummery, P., & Wen, K. (2008). Characterisation and Modelling of Microstructure Heterogeneity in Nuclear Graphite. In INGSM-9, Netherlands.. Publication link: 3d141442-bab7-4e53-b939-ad91bf0a256d
  • Berre, C., Hall, G., Marsden, B., Fok, S. L., Marrow, T. J., & Mummery, P. (2008). Modelling of Nuclear Grade Graphite Using X-Ray Tomography Data. In SMINS, OECD(NE), In co-operation with the IAEA, Karlsruhe, Germany.. Publication link: 4545ba12-e3dd-4a78-a4d3-8cf6c2bc8470
  • Eason, E. D., Hall, G., Heys, G. B., Knott, J. F., Marsden, B. J., Preston, S. D., & Swan, T. (2008). The origins and use of the equivalent temperature concept. Journal of Nuclear Materials, 381(1-2), 106-113. DOI:10.1016/j.jnucmat.2008.07.016. Publication link: 45b7d2da-1633-4001-92c3-82abb94b5c04
  • Marsden, B. J., Hall, G. N., Wouters, O., Vreeling, J. A., & van der Laan, J. (2008). Dimensional and material property changes to irradiated Gilsocarbon graphite irradiated between 650 and 750 °C. Journal of Nuclear Materials, 381(1-2), 62-67. DOI:10.1016/j.jnucmat.2008.07.018. Publication link: 1a3d42c1-fe2f-4f1a-8642-94c1a3edd16b
  • Wang, H. T., Hall, G., Yu, S. Y., & Yao, Z. H. (2008). Numerical Simulation of Graphite Properties Using X-ray Tomography and Fast Multipole Boundary Element Method. Computer Modelling in Engineering & Sciences, 37(2), 153-174. DOI:10.3970/cmes.2008.037.153. Publication link: 198da4fa-c973-44e1-b398-213cef69b196
  • Eason, E. D., Hall, G. N., Marsden, B. J., & Heys, G. B. (2008). Development of a Young's modulus model for Gilsocarbon graphites irradiated in inert environments. Journal of Nuclear Materials, 381(1-2), 145-151. DOI:10.1016/j.jnucmat.2008.07.036. Publication link: 970c17b7-a3f6-4233-8b27-1d708edd724d

2007

  • Hall, G., Marsden, B., Jones, A., & James, D. (2007). X-ray tomography of irradiated graphite. In INGSM-8, Bakubung, South Africa.. Publication link: b32e5565-8d22-403e-84d6-a12de6bac91b

2006

  • Hall, G., Marsden, B., Vreeling, J. A., & Laan, J. (2006). Possibilities for the Microstructural Modelling of the Irradiation Properties of Graphites for Future High Temperature Reactors. In HTR-2006, South Africa.. Publication link: aeb041d7-5dbf-428a-aaac-7c6a27d5a948
  • Hall, G., Marsden, B. J., & Fok, S. L. (2006). The microstructural modelling of nuclear grade graphite. Journal of Nuclear Materials, 353(1-2), 12-18. DOI:10.1016/j.jnucmat.2006.02.082. Publication link: 96457bfe-b06f-4e90-b388-1cfcb3c38c0e
  • Jones, A., Marsden, B., Wen, K., Hall, G., Marrow, T. J., Hodgkins, A., & Joyce, M. (2006). Microstructural Characterisation of Nuclear Grade Graphite. In 7th International Nuclear Graphite Specialists Meeting (INGSM-7), ORNL.. Publication link: dba7162d-0f2a-4194-b841-b7b2571cd9b0

2005

  • Hall, G., Berre, C., Marsden, B., & Fok, A. S. (2005). Microstructural modelling. In IAEA Technical Working Group on Gas-Cooled Reactors, Manchester.. Publication link: 9c4a696f-314c-4ab2-9bd7-a4863a218fa5
  • Eason, E. D., Hall, G., & Marsden, B. (2005). Development of a model of dimensional change in AGR graphites irradiated in inert environments. In Ageing Management of Graphite Reactor Cores, Wales.. Publication link: 85272969-4407-41bb-8fe3-9ec1e93aaeb9
  • Marsden, B., Hall, G., & Fok, A. S. (2005). Descriptions and summary of national programmes in gas-cooled reactors - United Kingdom. In IAEA Technical Working Group on Gas-Cooled Reactors, Manchester.. Publication link: 20ccaed5-3758-4e8c-9410-8cea3688ac54
  • Tsang, D. K. L., Marsden, B. J., Fok, S. L., & Hall, G. (2005). Graphite thermal expansion relationship for different temperature ranges. Carbon, 43(14), 2902-2906. DOI:10.1016/j.carbon.2005.06.009. Publication link: c73cc1cb-832b-49a8-b027-8c68f1154e7a
  • Hall, G., Marsden, B., Wen, K., Berre, C., Babout, L., & Hodgkins, A. (2005). Ongoing microstructural studies at the University of Manchester. In 6th International Nuclear Graphite Specialists Meeting (INGSM-6), France.. Publication link: d40288e9-f482-4e4f-ae50-7ddf0c6b1bd7

2004

  • Hall, G., & Marsden, B. (2004). Methods for the prediction of graphite irradiation dimensional and property changes in pressure tube reactor graphite. In International Conference on Pressure Tube Reactors: Problems and Solutions, Russia.. Publication link: 38ac0507-7d8e-49ff-bcef-81f308a91ea5

2003

  • Hall, G., & Marsden, B. (2003). Finite element analysis of crystals. In Finite element analysis of crystals.. Publication link: 9901a7ff-7f76-45fc-b6d1-29d3f2225fe0
  • Hall, G., Marsden, B. J., Fok, S. L., & Smart, J. (2003). The relationship between irradiation induced dimensional change and the coefficient of thermal expansion: A modified Simmons relationship. Nuclear Engineering and Design, 222(2-3), 319-330. DOI:10.1016/S0029-5493(03)00035-9. Publication link: 89e7f18f-202e-42ac-b475-2ca281ba642b
  • Marsden, B., Fok, S. L., & Hall, G. (2003). Descriptions and summary of national programmes in gas-cooled reactors - United Kingdom. In 18th Technical Working Group on Gas Cooled Reactors (TWG-GCR-18), Turkey.. Publication link: 26dd52bd-4b65-476c-a2b9-c4e066d38cae
  • Hall, G., Marsden, B., & Fok, S. L. (2003). The microstructural modelling of nuclear grade graphite. In 4th International Nuclear Graphite Specialists Meeting (INGSM-4), Japan.. Publication link: 1348b5be-989a-409a-8cff-b9a6d1c209de
  • Marsden, B., Fok, S. L., & Hall, G. (2003). High temperature gas-cooled reactor core design future material consideration. In International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP2003), Japan.. Publication link: 3304f187-1046-43af-918a-7179bf5ed0bc
  • Marsden, B., Fok, S. L., & Hall, G. (2003). Comparison of UK, American and Japanese unirradiated graphite CTE methodologies. In 18th Technical Working Group on Gas Cooled Reactors (TWG-GCR-18), Turkey.. Publication link: 3d0cc07e-28ae-4437-a87d-86c85d756abf
  • Hall, G., & Marsden, B. (2003). Microstructural modelling of nuclear grade graphite. In Universities Nuclear Technology Forum, Enlgand.. Publication link: fc1e3b60-b89e-480f-9f76-02d906ebc22f

2002

  • Hall, G., Marsden, B., Fok, A., & Smart, J. (2002). The relationship between irradiation induced dimensional change and the coefficient of thermal expansion: A new look. In Conference on High Temperature Reactors (HTR-2002), the Netherlands.. Publication link: ae50027f-ba8e-4ec2-b73b-b088d40cf178

1998

  • Hall, G., & Marsden, B. (1998). Nuclear Graphite Ageing and Turnaround. (Nuclear Graphite Ageing and Turnaround). No publisher name.. Publication link: aa5b3b6a-7cf0-453b-938e-1ed5a857a85e