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Mark N Mitchell
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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
842008
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
282007
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
252013
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
242012
PBMR reactor design and development
PJ Venter, MN Mitchell, F Fortier
IASMiRT, 2005
242005
Next generation nuclear plant phenomena identification and ranking tables (pirts)
HCG PIRT
152008
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
92007
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
82016
Identification of the key parameters defining the life of graphite core components
MN Mitchell
IASMiRT, 2005
82005
Criteria for Graphite Core Components (GCC)-ASME Nuclear Codes and Standards
MN Mitchell
9th International Graphite Specialist's Meeting, 2009
62009
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
62004
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
52008
Requirements for the Design and Manufacture of the Ceramic Internals of the PBMR. 2009
MN Mitchell
PBMR Clasified Internal Document, 0
5
The design of the PBMR core structures
MN Mitchell
Fifth International Nuclear Graphite Specialists Meeting, 12-9, 2004
32004
Graphite and Ceramic Coated Particles for the HTR
H Nabielek, M Mitchell
Advanced Materials for Sustainable Developments: Ceramic Engineering and …, 2010
22010
Requirements for the Design and Manufacture of the Ceramic Internals of the PBMR, in
M Mitchell
PBMR Classified internal document, 2009
22009
Materials selection for advanced high temperature gas cooled reactors
MN Mitchell, K Smit
Energy Materials 1 (3), 171-178, 2006
22006
Presentation to Fifth International Nuclear Graphite Specialists Meeting
MN Mitchell
Plas Tan-Y-Bwlch, Maentwrog, Gwynedd, United Kingdom, 2004
22004
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
12023
Formation of loading cones in the PBMR-core
HF Niessen, MN Mitchell
Numerical Modeling in Micromechanics via Particle Methods, 45-51, 2017
12017
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