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J.E. Hench

Observed names: Hench, J. E., J. E. Hench, J. Hench
Observed institution: General Electric (United States)
OpenAlex ID: A5083166555
Two-Dimensional Diffuser Performance With Subsonic, Two-Phase, Air–Water Flow
1972 · J. E. Hench, J. P. Johnston · Journal of Basic Engineering · 36
Correlation of critical heat flux data for application to boiling water reactor conditions. Final report
1981 · J.E. Hench, Jay Gillis · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 7
Nine-rod Critical Heat Flux Investigation at 1000 Psia
1966 · J.E. Hench, Robert F. Boehm · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 5
Design Basis for Critical Heat Flux Condition in Boiling Water Reactors.
1966 · J. M. Healzer, J.E. Hench, et al. · University of Michigan Library Repository · 4
The Effect of Fuel Rod Failure on Emergency Core Cooling System Design for Boiling Water Reactors
1971 · J. E. Hench, D. J. Liffengren · Nuclear Technology · 1
Turbine Flowmeter Calibration and Instrumented Fuel Assembly Pressure Drop. Garigliano Development Program
1965 · Diego G. Oliva, J.E. Hench · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1
Compact simulator for on-site reactor transient analysis and operator training
1983 · Chang Mook Kang, J.E. Hench · Transactions of the American Nuclear Society
Safety parameter display system for the River Bend nuclear station
1981 · E.L. Hammond, J.E. Hench · Transactions of the American Nuclear Society
BWR/6 emergency core cooling system
1974 · J.E. Hench · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Closure to “Discussion of ‘Two-Dimensional Diffuser Performance With Subsonic, Two-Phase, Air–Water Flow’” (1972, ASME J. Basic Eng., 94, pp. 119–121)
1972 · J. E. Hench, J. P. Johnston · Journal of Basic Engineering
Authors
1971 · P. L. Rittenhouse, R. A. Dean, et al. · Nuclear Technology
Effect of Fuel Rod Failure on Emergency Core Cooling System Design for Bwr's.
1970 · J.E. Hench, D.J. Liffengren · Transactions of the American Nuclear Society
General Electric Atomic Power Equipment Department Report GEAP-4492
1964 · Hench, J. E. · University of North Texas Digital Library (University of North Texas)
Transition and Film Boiling Data at 600, 1000, and 1400 psia in Forced Convection Heat Transfer to Water
1964 · US Atomic Energy Commission (AEC), J. Hench, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
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Works count: 14
Citation count: 54
H-index: 4
I10-index: 1
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