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R.A.U. Huddle

Observed names: Huddle, R.A.U., R. A. U. Huddle, R.A.U Huddle
OpenAlex ID: A5071024773
Alloys of Magnesium
1957 · R.A.U. Huddle, John Laing, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 14
The Possibilities of Achieving High Temperatures in a Gas Cooled Reactor
1959 · L.R. Shepherd, R.A.U. Huddle, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 5
40. Metals and alloys for very high temperature reactors
1975 · R. A. U. Huddle · 4
COATED PARTICLE FUEL FOR THE DRAGON REACTOR EXPERIMENT. Project DRAGON.
1962 · R.A.U. Huddle, J.R.C. Gough, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 4
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PAPER 17 The Influence of HTR Helium on the Behaviour of Metals in High Temperature Reactors
1971 · R. A. U. Huddle · 3
Review of Research and Development Work for the Dragon Project
1964 · L.R. Shepherd, Hans de Bruijn, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 3
Influence of Fabrication Parameters on the Incidence of Spearhead Attack in Coated Particle Fuel.
1969 · R.A.U. Huddle, K. Mayr, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2
Fuel Elements for High-temperature Reactors: Basic Materials Philosophy of the Dragon Programme.
1969 · R.A.U. Huddle · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1
The Development of Coated-particle Fuel for High-temperature Reactors
1966 · R.A.U. Huddle · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1
41 A Catalytic Mechanism of Anodic Inhibition in Metallic Corrosion
1957 · R.A.U Huddle, P.J. Anderson · Advances in catalysis · 1
The fuel element programme. Project DRAGON
2025 · Huddle, R.A.U. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Htr Direct Cycle: Engineering Possibilities and Material Requirements.
1970 · Geoff Lockett, R.A.U. Huddle · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Coated Particle Ceramic Fuel for the Dragon Reactor.
1968 · R.A.U. Huddle · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Dragon Reactor Fuel.
1966 · R.A.U. Huddle · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
High Temperature Reactor Materials.
1966 · R.A.U. Huddle, J.F.G. Condé, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
COST OF COATED PARTICLE FUEL FOR A HIGH-TEMPERATURE REACTOR PROGRAMME. Project DRAGON.
1965 · R.A.U. Huddle, M.S.T. Price, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
THE MANUFACTURE OF THE FIRST CHARGE OF FUEL AND FUEL ELEMENTS FOR THE DRAGON REACTOR. Project DRAGON.
1965 · R.A.U. Huddle, J.F.G. Condé, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Recent High Temperature Irradiation Experiments on Coated Particle Fuel for the Dragon Reactor
1964 · R.A.U. Huddle, P. Barr, et al. · Transactions of the American Nuclear Society
Fundamental Aspects of the Development and Behavior of Coated-partical Fuel for the Dragon Reactor Experiment
1963 · R.A.U. Huddle · Transactions of the American Nuclear Society
The "dragon" Project and Its Reactor Experiments
1960 · L.R. Shepherd, Geoff Lockett, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
The Dragon Reactor, Development and Design of the Htgc
1960 · Geoff Lockett, R.A.U. Huddle · Nuclear Power
Anodic Treatment of Uranium Metal
1959 · R.A.U. Huddle, Oliver Flint · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
The Resistance of Binary Aluminium Alloys to Corrosion by Water at High Temperatures and Pressures
1956 · R.A.U. Huddle, N.J.M. Wilkins · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Corrosion of Zirconium. Exploratory Tests on Tantalum and Niobium Alloys in Distilled Water
1952 · R.A.U. Huddle, C.F. Britton · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Works count: 24
Citation count: 38
H-index: 4
I10-index: 1
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