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Richard L. Moore

Observed names: Moore, R. L., Moore, Richard, Moore, Richard L., Moore, Richard Leroy, Moore,Richard L, Moore,Richard L., R Moore, R. L. Moore, R. Moore, R.L Moore, R.L. Moore, Richard L Moore, Richard Leroy Moore, Richard Moore
OpenAlex ID: A5048920682
The ARIES-AT advanced tokamak, Advanced technology fusion power plant
2005 · Farrokh Najmabadi, A. Abdou, et al. · Fusion Engineering and Design · 230
The ARIES-CS Compact Stellarator Fusion Power Plant
2008 · F. Najmabadi, A. R. Raffray, et al. · Fusion Science & Technology · 144
MOCUP: MCNP-ORIGEN2 coupled utility program
1995 · R Moore, USDOE, Washington, DC (United States), et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 91
A recent version of MELCOR for fusion safety applications
2010 · Brad J. Merrill, Paul W. Humrickhouse, et al. · Fusion Engineering and Design · 61
Modifications to the MELCOR code for application in fusion accident analyses
2000 · B.J Merrill, R.L Moore, et al. · Fusion Engineering and Design · 61
Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor
2004 · H. Oh, PhD Chang, Cliff Davis, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 53
NGNP Point Design - Results of the Initial Neutronics and Thermal-Hydraulic Assessments During FY-03, Rev. 1
2003 · Philip E. MacDonald, James W. Sterbentz, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 49
ARIES-AT safety design and analysis
2005 · D.A. Petti, B.J. Merrill, et al. · Fusion Engineering and Design · 37
Analyses of loss of vacuum accident (LOVA) in ITER
2000 · T. Honda, H.-W. Bartels, et al. · Fusion Engineering and Design · 36
ITER reference accidents
1998 · H.-W. Bartels, A. Poucet, et al. · Fusion Engineering and Design · 32
Safety Assessment of the ARIES Compact Stellarator Design
2008 · B. J. Merrill, L. A. El-Guebaly, et al. · Fusion Science & Technology · 31
Numerical simulation of gas and particle flow in a high-velocity oxygen-fuel (HVOF) torch
1995 · C. H. Chang, R. L. Moore · Journal of Thermal Spray Technology · 30
Development of a Supercritical Carbon Dioxide Brayton Cycle: Improving PBR Efficiency and Testing Material Compatibility
2004 · Chang Ho Oh, T.M. Lillo, et al. · 29
Development of a Supercritical Carbon Dioxide Brayton Cycle: Improving PBR Efficiency and Testing Material Compatibility - 2004 Annual Report
2004 · Chang Oh, Thomas Lillo, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 26
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Brayton Cycle for High-Temperature Gas-Cooled Reactors
2005 · Chang H. Oh, Richard L. Moore · Nuclear Technology · 24
Oxygen reactivity of a carbon fiber composite
2003 · T.D Marshall, R.J Pawelko, et al. · Fusion Engineering and Design · 13
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A preliminary assessment of beryllium dust oxidation during a wet bypass accident in a fusion reactor
2009 · Brad J. Merrill, Richard L. Moore, et al. · Fusion Engineering and Design · 12
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The Next Generation Nuclear Plant - Insights Gained from the INEEL Point Design Studies
2004 · MacDonald, Philip E., Baxter, A. M., et al. · University of North Texas Digital Library (University of North Texas) · 12
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Safety and Environment Assessment of ARIES-AT
2001 · D. A. Petti, B. J. Merrill, et al. · Fusion Technology · 9
Safety Analysis Results for ITER In-Vessel Loss of Coolant Events
1997 · D. A. Petti, B. J. Merrill, et al. · Journal of Fusion Energy · 9
Comparison of Thermal and Mechanical Responses of the Three Mile Island Unit 2 Reactor Vessel
1989 · Gary L. Thinnes, Richard L. Moore · Nuclear Technology · 9
Modular Pebble Bed Reactor
2000 · Andrew C. Kadak, R. G. Ballinger, et al. · DSpace@MIT (Massachusetts Institute of Technology) · 8
Three Mile Island Unit 2 Degraded Core Heatup and Cooldown Analysis
1989 · Richard L. Moore, Daniel W. Golden, et al. · Nuclear Technology · 8
Modular Pebble-Bed Reactor Project: Laboratory-Directed Research and Development Program FY 2002 Annual Report
2002 · David Andrew Petti, Thomas James Dolan, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 6
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Pedigree Analysis of the MELCOR 1.8.2 Code to be Used for ITER?s Report Preliminary on Safety
2007 · Richard L. Moore, Brad J. Merrill · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 5
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Works count: 56
Citation count: 1,076
H-index: 15
I10-index: 18
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