| Oxidation experiments and theoretical examinations on graphite materials relevant for the PBMR HK Hinssen, K Kühn, R Moormann, B Schlögl, M Fechter, M Mitchell Nuclear Engineering and Design 238 (11), 3018-3025, 2008 | 91 | 2008 |
| A numerical stress based approach for predicting failure in NBG-18 nuclear graphite components with verification problems MP Hindley, MN Mitchell, C Erasmus, R McMurtry, TH Becker, DC Blaine, ... Journal of Nuclear Materials 436 (1-3), 175-184, 2013 | 33 | 2013 |
| PBMR reactor design and development PJ Venter, MN Mitchell, F Fortier Proceedings of the 18th International Conference on Structural Mechanics in …, 2005 | 30* | 2005 |
| Observations in the statistical analysis of NBG-18 nuclear graphite strength tests MP Hindley, MN Mitchell, DC Blaine, AA Groenwold Journal of nuclear materials 420 (1-3), 110-115, 2012 | 29 | 2012 |
| Integrated design approach of the pebble BeD modular reactor using models PJ Venter, MN Mitchell Nuclear Engineering and Design 237 (12-13), 1341-1353, 2007 | 28 | 2007 |
| Next generation nuclear plant phenomena identification and ranking tables (pirts) HCG PIRT | 15 | 2008 |
| Assessment of the loads on a solid centre reflector of a Pebble Bed Reactor using DEM techniques MN Mitchell, AG Polson Nuclear engineering and design 237 (12-13), 1332-1340, 2007 | 12 | 2007 |
| Codes and standards for ceramic composite core materials for High Temperature Reactor applications JW Geringer, Y Katoh, S Gonczy, T Burchell, M Mitchell, M Jenkins, ... Nuclear Engineering and Design 405, 112158, 2023 | 9 | 2023 |
| Power variability analysis of megawatt-scale solar photovoltaic installations M Mitchell, M Campbell, K Klement, M Sedighy 2016 IEEE Electrical Power and Energy Conference (EPEC), 1-4, 2016 | 9 | 2016 |
| Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 5: Graphite PIRTs TD Burchell, R Bratton, B Marsden, M Srinivasan, S Penfield, M Mitchell, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2008 | 8 | 2008 |
| Identification of the Key Parameters Defining the Life of Graphite Core Component MN Mitchell 18th International Conference on Structural Mechanics in Reactor Technology …, 2005 | 8 | 2005 |
| Criteria for Graphite Core Components (GCC)-ASME Nuclear Codes and Standards MN Mitchell 9th International Graphite Specialist's Meeting, 2009 | 6 | 2009 |
| A Study into the Key Factors Influencing the Design Life of a PBMR Side Reflector Block MN Mitchell Plas Tan-Y-Bwlch, Maentwrog Gwynedd, United Kingdom, 2004 | 6 | 2004 |
| Requirements for the Design and Manufacture of the Ceramic Internals of the PBMR. 2009 MN Mitchell PBMR Clasified Internal Document, 0 | 5 | |
| Graphite and Ceramic Coated Particles for the HTR H Nabielek, M Mitchell Advanced Materials for Sustainable Developments: Ceramic Engineering and …, 2010 | 4 | 2010 |
| Formation of loading cones in the PBMR-core HF Niessen, MN Mitchell Numerical Modeling in Micromechanics via Particle Methods, 45-51, 2017 | 2 | 2017 |
| Requirements for the Design and Manufacture of the Ceramic Internals of the PBMR, in M Mitchell PBMR Classified internal document, 2009 | 2 | 2009 |
| Nuclear Reactor M Mitchell, J Vorster US Patent App. 11/573,615, 2007 | 2 | 2007 |
| Materials selection for advanced high temperature gas cooled reactors MN Mitchell, K Smit Energy Materials 1 (3), 171-178, 2006 | 2 | 2006 |
| Presentation to Fifth International Nuclear Graphite Specialists Meeting MN Mitchell Plas Tan-Y-Bwlch, Maentwrog, Gwynedd, United Kingdom, 2004 | 2 | 2004 |
Michael HindleyUSNCVerified email at mechcae.com
