Author

W.A. Sutherland

Observed names: W Sutherland, W. A. Sutherland, W. Sutherland, Wm. A. Sutherland

Institutions: Japan Atomic Energy Agency, General Electric (United States)

Observed institutions: Japan Atomic Energy Agency, General Electric (United States)

OpenAlex ID: A5035470461

Critical flow of saturated and subcooled water at high pressure. [PWR; BWR]

1975 · Giovanna Sozzi, W.A. Sutherland · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 47

Heat-Transfer and Flow-Friction Characteristics of Crossed-Rod Matrices

1960 · A. L. London, J. W. Mitchell, et al. · ASME Journal of Heat and Mass Transfer · 28

Heat transfer in an annulus with variable circumferential heat flux

1964 · W.A. Sutherland, W.M. Kays · International Journal of Heat and Mass Transfer · 18

Improved heat-transfer performance with boundary-layer turbulence promoters

1967 · W.A. Sutherland · International Journal of Heat and Mass Transfer · 16

Heat Transfer in Parallel Rod Arrays

1966 · W. A. Sutherland, W. M. Kays · ASME Journal of Heat and Mass Transfer · 13

BWR small break LOCA counterpart tests at ROSA-III and FIST test facilities

1987 · Y. Koizumi, H. Nakamura, et al. · Nuclear Engineering and Design · 5

BWR Full Integral Simulation Test (FIST) Phase II test results and TRAC-BWR model qualification

1985 · W Sutherland, M Alamgir, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 5

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1986 · Mitsuhiro Suzuki, J.A. Findlay, et al. · Nuclear Engineering and Design · 4

BWR Full Integral Simulation Test (FIST). Phase I test results

1984 · W Hwang, M Alamgir, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 4

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Experimental Heat Transfer in Rod Bundles.

1969 · W.A. Sutherland · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 4

1987 · Hiroshige Kumamaru, Mitsuhiro Suzuki, et al. · Nuclear Engineering and Design · 3

Discussion: “Fully Developed Turbulent Flow in Annuli” (Brighton, J. A., and Jones, J. B., 1964, ASME J. Basic Eng., 86, pp. 835–842)

1964 · W. A. Sutherland · Journal of Basic Engineering · 2

Heat Transfer in Seven-rod Clusters. Influence of Liner and Spacer Geometry on Superheat Fuel Performance.

1966 · H. Hoffmann, C.W. Miller, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1

Using TRAC to apply integral test experience to reactor system analysis

1984 · Md. Alamgir, W.A. Sutherland · Transactions of the American Nuclear Society

FIST Small Break Accident Analysis with BWR TRACB02 — Pretest Predictions

1984 · Md. Alamgir, Wm. A. Sutherland · Springer eBooks

BWR Refill-Reflood Program: Task 4. 3 - Single Heated Bundle. Final report

1983 · W. Sutherland, J. Barton, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)

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Condensation effects in large scale BWR safety experiments

1983 · W.A. Sutherland

Blowdown heat transfer review of recent results

1975 · General Electric Co., San Jose, Calif. (USA). Boiling Water Reactor Systems Dept., W Sutherland · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)

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BWR blowdown heat transfer experiment

1975 · W.A. Sutherland, R.T. Lahey · Transactions of the American Nuclear Society

HEAT TRANSFER IN PARALLEL ROD ARRAYS (thesis)

1965 · W.A. Sutherland, W. M. Kays · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)

Heat transfer in an annulus with variable circumferential heat flux

1964 · W.A. Sutherland, W.M. Kays · International Journal of Heat and Mass Transfer

HEAT TRANSFER AND FLOW FRICTION CHARACTERISTICS OF CROSSED-ROD MATRICES. Technical Report No. 41

1959 · A. L. London, J. W. Mitchell, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)

Works count: 22

Citation count: 150

H-index: 5

I10-index: 5