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R.A. Verrall

Observed names: R Verrall, R. A. VERRALL, R. A. Verrall, R. Verrall, R.A Verrall, R.A. VERRALL, Richard A Verrall, Verrall, R. A., Verrall, R.A.
OpenAlex ID: A5018807411
Diffusion-accommodated flow and superplasticity
1973 · M.F Ashby, R.A Verrall · Acta Metallurgica · 1,445
Radiation damage effects in zirconia
1999 · K.E. Sickafus, Hj. Matzke, et al. · Journal of Nuclear Materials · 362
Interface controlled diffusional creep
1983 · E. Arzt, M.F. Ashby, et al. · Acta Metallurgica · 325
Micromechanisms of flow and fracture, and their relevance to the rheology of the upper mantle
1978 · M. F. Ashby, R. A. Verrall · Philosophical Transactions of the Royal Society of London Series A Mathematical and Physical Sciences · 284
Microstructural features of SIMFUEL — Simulated high-burnup UO2-based nuclear fuel
1991 · P.G. Lucuta, R.A. Verrall, et al. · Journal of Nuclear Materials · 200
Ceramic breeder material development
1998 · N. Roux, S. Tanaka, et al. · Fusion Engineering and Design · 114
Silicon carbide as an inert-matrix for a thermal reactor fuel
1999 · R.A. Verrall, M.D. Vlajic, et al. · Journal of Nuclear Materials · 100
Radiation damage effects in cubic-stabilized zirconia irradiated with 72 MeV I+ ions
1998 · Kurt E Sickafus, Hansjoachim Matzke, et al. · Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms · 96
Thermal conductivity of hyperstoichiometric SIMFUEL
1995 · P.G. Lucuta, Hj. Matzke, et al. · Journal of Nuclear Materials · 87
Summary of experimental results for ceramic breeder materials
1995 · N Roux, G Hollenberg, et al. · Fusion Engineering and Design · 78
Thermal conductivity of SIMFUEL
1992 · P.G. Lucuta, Hj. Matzke, et al. · Journal of Nuclear Materials · 66
Application of bound theorems for creeping solids and their application to large strain diffusional flow
1978 · M.F. Ashby, G.H. Edward, et al. · Acta Metallurgica · 49
Modelling of UO2-based SIMFUEL thermal conductivity The effect of the burnup
1994 · P.G. Lucuta, Hj. Matzke, et al. · Journal of Nuclear Materials · 43
Thermodynamic treatment of uranium dioxide based nuclear fuel
2007 · W. T. Thompson, B. J. Lewis, et al. · International Journal of Materials Research (formerly Zeitschrift fuer Metallkunde) · 40
Migration behaviour of iodine in nuclear fuel
2001 · W.H. Hocking, R.A. Verrall, et al. · Journal of Nuclear Materials · 40
Deformation‐Mechanism Maps for LiF and NaCl
1977 · R. A. VERRALL, R. J. FIELDS, et al. · Journal of the American Ceramic Society · 36
Burn and bury option for plutonium
1999 · Kurt E. Sickafus, Robert J. Hanrahan, et al. · Joint Research Centre (European Commission) · 34
Specific heat measurements of UO2 and SIMFUEL
1996 · R.A. Verrall, P.G. Lucuta · Journal of Nuclear Materials · 31
Specific heat of UO2-based SIMFUEL
1997 · Hj. Matzke, P.G. Lucuta, et al. · Journal of Nuclear Materials · 28
EXOTIC-7: Irradiation of ceramic breeder materials to high lithium burnup
1996 · J.G. van der Laan, H. Kwast, et al. · Journal of Nuclear Materials · 28
Canadian ceramic breeder technology: recent results
1995 · P Gierszewski, H Hamilton, et al. · Fusion Engineering and Design · 28
Canadian ceramic breeder sphere-pac technology: capability and recent results
1991 · J.D. Sullivan, C.L. Brayman, et al. · Fusion Engineering and Design · 27
Formation and behaviour of barium silicate in UO2-based SIMFUEL
1991 · Hj. Matzke, P.G. Lucuta, et al. · Journal of Nuclear Materials · 24
Irradiation of lithium zirconate pebble-bed in BEATRIX-II Phase II
1994 · R.A. Verrall, O.D. Slagle, et al. · Journal of Nuclear Materials · 19
Modeling Unusual Tritium Release Behavior from Li2O
1989 · J. P. Kopasz, S. W. Tam, et al. · Fusion Technology · 18
Works count: 70
Citation count: 3,777
H-index: 23
I10-index: 35
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