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James F. Lime

Observed names: J F Lime, J Lime, J. F. Lime, J. Lime, J.F. Lime, Lime, J. F., Lime, J.F.
Observed institution: Los Alamos National Laboratory
OpenAlex ID: A5035403355
Analysis of an AP600 intermediate-size loss-of-coolant accident
1995 · Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology, B. Boyack, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 10
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Intermediate-break LOCA analyses for the AP600 design
1995 · Los Alamos National Lab., NM (United States), B Boyack, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 5
TRAC User's Guide
1985 · B.E. Boyack, Heinrich Stumpf, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 5
Updated TRAC analysis of an 80% double-ended cold-leg break for the AP600 design
1995 · Los Alamos National Lab., NM (United States), J Lime, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 3
TRAC large-break loss-of-coolant accident analysis for the AP600 design
1994 · J.F. Lime, B.E. Boyack · University of North Texas Digital Library (University of North Texas) · 3
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A TRAC-PF1/MOD1 analysis of the Ginna tube-rupture event on January 25, 1982
1987 · J.F. Lime, R.P. Jenks · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2
Los Alamos PWR decay-heat-removal studies. Summary results and conclusions
1986 · B E Boyack, R J Henninger, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2
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Rapid-response analysis of the Davis-Besse loss-of-feedwater event on June 9, 1985
1986 · J.F. Lime, Bahram Nassersharif, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2
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A TRAC model of the Los Alamos National Laboratory DELTA loop facility
2003 · J.F. Lime, J. Zhang · University of North Texas Digital Library (University of North Texas) · 1
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Development of Transient-Reactor Analysis Code (TRAC) for real-time applications
1997 · Los Alamos National Lab., NM (United States), G Niederauer, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1
One-dimensional TRAC calculations of main steam line break events for the updated PIUS 600 advanced reactor design
1993 · Harmony, S. C., Steiner, J. L., et al. · University of North Texas Digital Library (University of North Texas) · 1
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One-dimensional TRAC calculations of a pump-trip scram for the PIUS 600 advanced reactor design
1993 · J.L. Steiner, J.F. Lime, et al. · University of North Texas Digital Library (University of North Texas) · 1
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TRAC-PF1 choked-flow model
1983 · Sahota, J.F. Lime · University of North Texas Digital Library (University of North Texas) · 1
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Pump-operation effects on main steam line breaks for a pressurized water reactor
1982 · J.F. Lime, J.E. Willcutt · Transactions of the American Nuclear Society · 1
BEACON/MOD: a computer program for thermal-hydraulic analysis of nuclear reactor containments - user's manual
1980 · C.R. Broadus, R.J. Doyle, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1
The GINNA Tube-Rupture Event: A Plant-Transient Benchmark for TRAC
2024 · Lime, J.F., Jenks, R.P. · Canadian Nuclear Society Proceedings
Task completion report for update FXCFM
1998 · Los Alamos National Lab., NM (United States), R Steinke, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Reactor scram events in the updated PIUS 600 advanced reactor design
1994 · B.E. Boyack, J.L. Steiner, et al. · University of North Texas Digital Library (University of North Texas)
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Loss of Offsite Power Transients in the Updated PIUS 600 Advanced Reactor Design
1994 · Brent E. Boyack, James L. Steiner, et al. · ASME International Mechanical Engineering Congress and Exposition (IMECE)
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Large–Break Loss–of–Coolant Accidents in the Updated PIUS 600 Advanced Reactor Design
1994 · James L. Steiner, Stephen C. Harmony, et al. · ASME International Mechanical Engineering Congress and Exposition (IMECE)
TRAC loss-of-coolant accident analyses of the Savannah River production reactors
1990 · J.F. Lime, F.E. Motley · Transactions of the American Nuclear Society
TRAC (Transient Reactor Analysis Code) analyses of Savannah River 1985 L-Area test series
1990 · Jay S. Elson, J.F. Lime · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
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Los Alamos PWR feed-and-bleed studies summary results and conclusions
1985 · Boyack, B. E., Henninger, R. J., et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
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Comparison of BEACON and COMPARE reactor cavity subcompartment analyses
1984 · Michael W. Burkett, E.S. Idar, et al. · Transactions of the American Nuclear Society
LOFW feed-and -bleed in a Westinghouse three-loop low-head safety-injection PWR
1984 · J.F. Lime · Transactions of the American Nuclear Society
Works count: 33
Citation count: 39
H-index: 3
I10-index: 1
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