Author

R. Blackstone

Observed names: Blackstone, R., R Blackstone, R. BLACKSTONE

Institution: Energy Research Centre of the Netherlands

Observed institution: Energy Research Centre of the Netherlands

OpenAlex ID: A5041079002

The expansion of silicon carbide by neutron irradiation at high temperature

1971 · R. Blackstone, E.H. Voice · Journal of Nuclear Materials · 73

Radiation creep of graphite. An introduction

1977 · R. Blackstone · Journal of Nuclear Materials · 26

The irradiation creep in reactor graphites for HTR applications

1976 · H.J. Veringa, R. Blackstone · Carbon · 17

Dimensional and physical property changes of high temperature-reactor graphites, pyrocarbons and fuel bodies irradiated at temperatures in the range 600–1200°C

1971 · M.R. Everett, L.W. Graham, et al. · Carbon · 7

117. High temperature radiation induced creep in graphite

1969 · R Blackstone, L.W Graham, et al. · Carbon · 5

Radiation Creep of Graphite. an Introduction

1977 · R. BLACKSTONE · Elsevier eBooks · 3

184. Experiments on the irradiation of graphite at high temperatures

1965 · R Blackstone, P.S Sens, et al. · Carbon · 3

Irradiation data on Gilsocarbon graphites for high temperature nuclear reactors

1969 · R. Blackstone, L.W. Graham, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2

Graphite Materials Data for High-temperature Nuclear Reactors.

1971 · M.R. Everett, R. Blackstone, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1

87. The irradiation induced creep in fuel compact materials for H.T.R. applications

1976 · H. Veringa, R. Blackstone, et al. · Carbon

Review on Characterization Methods applied to HTR-Fuel Element Components

1976 · K. Koizlik, M.R. Everett, et al.

High temperature irradiation enhanced creep in graphites for HTR application

1975 · H.J Veringa, R Blackstone · Carbon

Graphite-irradiation in high-temperature reactors. III

1974 · R. Blackstone · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)

Quality Control Procedures on Graphite, Pyrocarbon and Siliconcarbide

1974 · K. Koizlik, P. D. Frampton, et al.

171. Effects of changes in irradiation temperature on the irradiation behaviour of graphites and matrix materials

1973 · W.W Delle, M.R Everett, et al. · Carbon

167. Irradiation behaviour of gilsocarbon graphites

1973 · R Blackstone, H.J Veringa, et al. · Carbon

Irradiation behavior of HTR graphites

1973 · M.R. Everett, R. Blackstone, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)

Irradiation behaviour of HTR fuel compacts

1973 · M.R. Everett, R. Blackstone

The irradiation behaviour of HTR graphites

1973 · M.R. Everett, R. Blackstone, et al.

The characteristics of gilsocarbon graphite and its significance for the design of high temperature reactors

1972 · R. Krefeld, R. Blackstone, et al. · Carbon

Irradiation behaviour of nuclear graphites based on natural graphite filler

1972 · G. Spener, F.J. Herrman, et al. · Carbon

Irradiation behaviour of Gilsocarbon graphites

1972 · R. Blackstone, R. Krefeld, et al. · Carbon

15. Automatic devices for measuring dimensions, electrical resistivity and Young's modulus of irradiated graphite specimens

1972 · R. Blackstone, K. Heeringa, et al. · Emerald Group Publishing Limited eBooks

Graphite materials data for high temperature nuclear reactors. Dragon Project

1969 · M.R. Everett, R. Blackstone, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)

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112. Dimensional and physical property changes of H.T.R. graphites irradiated at temperatures in the range 600°-1200°C

1969 · M.R Everett, R Blackstone, et al. · Carbon

Works count: 35

Citation count: 137

H-index: 5

I10-index: 3