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J.S. Waddington

Observed names: J. S. WADDINGTON, J. S. Waddington, J.S Waddington
OpenAlex ID: A5110094771
The importance of shock wave profile in explosive loading experiments
1964 · A.S. Appleton, J.S. Waddington · Acta Metallurgica · 38
The effect of irradiation on the high temperature fracture of stainless steel
1967 · J.S. Waddington, K. Lofthouse · Journal of Nuclear Materials · 24
Some observations of discontinuous yielding phenomena in copper, nickel and aluminium after shock loading
1965 · A. S. Appleton, J. S. Waddington · Philosophical magazine · 24
Fuel Failures in the Dodewaard Boiling Water Reactor
1977 · D. Cordall, R. M. Cornell, et al. · Nuclear Technology · 11
On the conditions affecting the mechanism of fracture at high temperatures
1968 · J. S. Waddington · Philosophical magazine · 8
The effect of pre-strain on the high temperature ductility of a stainless steel
1970 · J.S. Waddington, H.E. Evans · Journal of Nuclear Materials · 6
On the apparent kinetics of creep cavity nucleation
1969 · H. E. Evans, J. S. Waddington · Philosophical magazine · 6
The annealing of creep fracture damage in a stainless steel
1969 · H.E. Evans, J.S. Waddington · Journal of Nuclear Materials · 6
The fracture, by the triple point mechanism, of aluminium-20% zinc in the presence of a hydrostatic pressure
1967 · J.S Waddington, J.A Williams · Acta Metallurgica · 4
Aspects of the High-temperature Irradiation Embrittlement in Stainless Steels.
1967 · J.S. Waddington · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 3
30. The design and development of an improved CAGR fuel element for high power refuelling and extended irradiation
1985 · T. A. Seeley, R. D. Stacey, et al. · Emerald Group Publishing Limited eBooks · 1
Interaction Between UO 2 Pellets and Cladding in Water Reactor Fuel Pins
1977 · J. S. WADDINGTON, GEOFFREY ROBERTS, et al. · Journal of the American Ceramic Society · 1
5 The objectives and organisation of a national post-irradiation examination programme for commercial advanced gas-cooled reactor fuel
1981 · G. F. Hines, J. S. Waddington, et al. · Emerald Group Publishing Limited eBooks
Development of fuel elements for the AGR
1979 · J.S. Waddington, L.F.A. Raven, et al.
Material apsects of AGR fuel
1979 · J.S. Waddington, M.V. Speight · Transactions of the American Nuclear Society
Authors
1977 · E. L. Simmons, Donald J. Dudziak, et al. · Nuclear Technology
Mechanical properties of AGR cladding
1973 · J. Winton, D. Rhodes, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Design of Nuclear Plant for Maximum Availability.
1971 · J.S. Waddington, M.J. Whitmarsh-Everiss · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Effect of Rest Periods on the Accumulation of High Temperature Fracture Damage.
1971 · Geraldine K. Walker, Howard E. Evans, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Works count: 19
Citation count: 132
H-index: 6
I10-index: 4
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