W. C. Jochem, G. T. Mays, Randy
Belles, S. R. Greene, et al, National
Site Suitability and Spatial Modeling of Electrical Generation Sources,
Annual Meeting of the Association of American Geographers, Washington, D.C.,
April 2010.
S. R. Greene, The Energy Enterprise – An Energy Park Concept for the 21st
Century, American Institute of Chemical Engineers, Nashville, TN, November
2009.
G. T. Mays, W. C. Jochem, S. R.
Greene, R. J. Belles, M. S. Cetiner, and S. W. Hadley, Identifying and Characterizing Candidate Areas for Siting New Nuclear
Capacity in the United States, American Nuclear Society Winter Meeting,
Washington, DC, November 2009.
S. R. Greene, G. T. Mays, Development of a Siting Decision Tool for
Identifying and Characterizing Potential Electrical Generation Sites, 33rd
Governor’s Conference on the Environment – Empowering Our Future, Lexington,
KY, October 2009.
S. R. Greene, “The Tennessee Valley Energy Enterprise – A
Sustainable Energy Park Concept,” Chattanooga Technology Council meeting,
June 2009.
M. Crozat, S. R. Greene, and R.
Roser, Building an “Open Source” Flexible
and Extendible Energy Enterprise Model, Proceedings of the Workshop on Science
Based Nuclear Energy Systems Enabled by Advanced Modeling and Simulation at the
Extreme Scale Conference, U.S. Department of Energy’s Offices of Science and
Nuclear Energy, Washington, DC, May 2009.
S. R. Greene, G. F. Flanagan, and
A. P. Borole, Integration of
Biorefineries and Nuclear Cogeneration Power Plants – A Preliminary Analysis,
ORNL/TM-2008/102, Oak Ridge National Laboratory, Oak Ridge, TN, March 2009.
S. R. Greene, A. P. Borole, and G.
F. Flanagan, Technology, Process, and
Plant-Level Issues Associated with Integration of Nuclear Cogeneration Plants
and Biorefineries, American Nuclear Society Winter Meeting, 2008.
S. R. Greene, PICES – A Computer Code for Evaluation of Electric Utility Static
Generation Reliability, ORNL-5739, Oak Ridge National Laboratory, August
1981.
M. A. Kuliasha, S. R. Greene, and
W. P. Poore, Determining Appropriate Levels
of Generation System Reliability, The National Electric Reliability
Study: Technical Study Reports,
DOE/EP-0005, U. S. Department of Energy, April 1981.
Boiling Water
Severe Accident Analysis and Miscellaneous Reactor Safety
Sherrell R. Greene, The Canary, The Ostrich, and The Black Swan – An Historical Perspective on Our Understanding of BWR Severe Accidents and Their Mitigation, Proceedings of the International Meeting on Severe Accident Assessment and Management: Lessons Learned from Fukushima Daiichi, American Nuclear Society, San Diego, CA, November 12, 2012.
Juan Carbajo and Sherrell R.
Greene, Containment Failure Time and Mode
for a Low-Pressure Short-Term Station Blackout in a BWR-4 with Mark-III
Containment, Proceedings of the American Nuclear Society Winter Meeting,
San Francisco, CA, November 1993.
S. R. Greene, et al., Long Range Research and Development Plan –
Reactor-Based Technologies, Rev. 1, ORNL/MD/LTR-12, Oak Ridge National
Laboratory,1993.
S. R. Greene, R. T. Primm, et al.,
Compilation of Plutonium Disposition
Reactor Fuel Specifications, Rev. 0, ORNL/MD/LTR-1, Oak Ridge National
Laboratory, 1993.
R. H. Morris, S. E. Fisher, S. R.
Greene, MELCOR Simulation of a
Large-Break LOCA At the High Flux Isotope Reactor, CONF-930601,
Transactions of the American Nuclear Society, Vol. 68, 1993.
S. R. Greene, D. G. Morris, R. H.
Morris, B. W. Patton, and D. B Simpson, HFIR
MELCOR Severe Accident Analysis Model Version 1.0.0 Validation, ORNL/CF-284,
Oak Ridge National Laboratory.
P. T. Rhoads, Greene, S. R., Definition of the Existing Light-Water
Reactor (LWR) Alternative and Variants, ORNL/MD/LTR-22, Oak Ridge National
Laboratory, 1993.
S. R. Greene et al., MELCOR 1.8.2 Assessment: Comparison of Fuel Fission Product
Release Models to ORNL VI Fuel Fission Product Release Experiment,
ORNL/NRC/LTR-94/34, 1993.
C. R. Hyman, R. L. Sanders, S. R.
Greene, and S. A. Hodge, MELCOR
Modifications for SBWR Applications, Proceedings of the Twentieth Water
Reactor Safety Information Meeting, Bethesda, MD, 1992.
S. E. Fisher and S. R. Greene, A Preliminary Assessment of Hydrogen
Deflagration Issues for the High Flux Isotopes Reactor, ORNL/TM-2395, Oak
Ridge National Laboratory, October 1992.
S. R. Greene, S. A. Hodge, C. R.
Hyman, and R. L. Sanders, An Assessment
of MELCOR Modeling Modifications Required for the Simplified Boiling Water
Reactor, ORNL/NRC/LTR-92/11, Oak Ridge National Laboratory, May 1992.
C. R. Hyman, R. P. Taleyarkhan,
and S. R. Greene, Characterization of
Debris/Concrete Interactions for Advanced Research Reactors and Commercial BWR
Severe Accidents, CONF-911107—30, American Nuclear
Society Winter Meeting, 1991.
C. R. Hyman, R. P. Taleyarkhan,
and S. R. Greene, Characterization of
Debris/Concrete Interactions for Commercial BWR Mark II and Research Reactors
Severe Accidents, National Heat Transfer Conference, Minneapolis, MN, 1991.
C. R. Hyman, R. P. Taleyarkhan,
and S. R. Greene, Characterization of
Debris/Concrete Interactions for Advanced Research Reactor and Commercial BWR
Severe Accidents, Proceedings for the American Nuclear Society Winter
Meeting, 1991.
S. R. Greene, A. E. Levin, C. R.
Hyman, A. Sozer, and R. P. Taleyarkhan, BWR
Mark II Ex-Vessel Corium Interaction Analyses, NUREG/CR-5623,
ORNL/TM-11644, Oak Ridge National Laboratory, November 1991.
S. R. Greene, S. A. Hodge, C. R.
Hyman, B. W. Patton, and M. L. Tobias, The
Response of BWR Mark III Containments to Short-term Station Blackout Severe
Accident Sequences, NUREG/CR-5571, ORNL/TM-11549, Oak Ridge National
Laboratory, June 1991.
D. B. Simpson and S. R. Greene, Large Break Loss of Coolant Severe Accident
Sequences at the HFIR, International Topical Meeting on the Safety, Status
and Future of Noncommercial Reactors and Irradiation Facilities, Boise, Idaho,
October 1990.
S. R. Greene, “The Role of BWR Secondary Containments In Severe Accident Mitigation:
Issues and Insights From Recent Analyses,” Nuclear Engineering and Design, Volume 120, Issue 1, 1 June 1990,
Pages 75-86
S. R. Greene, et al., The Response of BWR Mark II and Mark III
Containments to Short-Term Station Blackout Severe Accident Sequences,
ORNL/NRC/LTR-89/13, Oak Ridge National Laboratory, 1990.
S. R. Greene and D. B. Simpson, Severe Accident Analysis at the High Flux
Isotope Reactor, American Nuclear Society Annual Meeting, Nashville, TN,
June 1990.
S. R. Greene, D. B. Simpson, and
R. P. Taleyarkhan, A Preliminary Modeling
and Analysis Framework- for Severe Accident Analyses of High Power Density
Research Reactors, IAEA-SM310/62P, International Symposium on Research
Reactor Safety, Operations, and Modifications, Chalk River, Ontario, Canada,
October 1989.
S. R. Greene, The Impact of
Drywell Shell Melt-Through on Peach Bottom Unit 2 Secondary Containment
Survivability, 1988.
S. R. Greene, Supercomputing and Reactor Safety, Vol. 21, No. 3, ORNL Review, Oak Ridge National
Laboratory, 1988.
S. R. Greene, Report of the Advanced Neutron Source Safety Workshop, Advanced Neutron Source Severe Accident
Analysis Program Overview, CONF-8810193, Knoxville, TN, October 25-26,
1988.
S. R. Greene, The Role of BWR Secondary Containments in Severe Accident
Mitigation: Issues and Insights
from Recent Analyses, NUREG/CR-0095, Proceedings of the 4th
Workshop on Containment Integrity, Arlington, VA, June 1988.
S. R. Greene, The Impact of BWR MK I Primary Containment Failure Dynamics on
Secondary Containment Integrity, CONF-8710111—6, Transactions of the 15th
Water Reactor Safety Information Meeting, Gaithersburg, MD, October 1987.
S. R. Greene and S. A. Hodge,
“ORNL Severe Accident Analysis for 25% Power Operation at the Shoreham Nuclear
Power Station,” June 18, 1987.
S. R. Greene, An Assessment of the Shoreham Nuclear Power Station’s Secondary
Containment Severe Accident Mitigation Capability, ORNL LTR Report to U.S.
Nuclear Regulatory Commission, June 26, 1987.
S. R. Greene, and S. A. Hodge, The Role of BWR MK I Secondary Containments
in Severe Accident Mitigation, CONF-8610135—41, Transactions of the 14th
Water Reactor Safety Information Meeting, Gaithersburg, MD, October 1986.
S. R. Greene, NATC – A Simple Model for Analysis of Single-Phase, Water Cooled,
Natural Convection Systems, ORNL/CR-85/345, Oak Ridge National Laboratory,
December 1985.
S. R. Greene, Realistic Simulation of Severe Accidents in BWRs - Computer Modeling
Requirements, NUREG/CR-2940, ORNL/TM-8517, Oak Ridge National Laboratory, 1984.
D. H. Cook, S. R. Greene, R. M.
Harrington, and S. A. Hodge, Loss of DHR
Sequences at Browns Ferry Unit One - Accident Sequence Analysis,
NUREG/CR-2973, ORNL/TM-8532, Oak Ridge National Laboratory, May 1983.
W. A. Condon, R. M. Harrington, S.
R. Greene, and S. A. Hodge, SBLOCA
Outside Containment at Browns Ferry Unit One – Accident Sequence Analysis, NUREG/CR2672,
Volume 1, ORNL/TM-8119/V1, Oak Ridge National Laboratory, November 1982.
S. R. Greene, Improvement of MARCH for BWR Applications, Proceedings of the 10th
Water Reactor Safety Information Meeting, Gaithersburg, MD, October 1982.
S. R. Greene, Application of MARCH to BWR Severe Accident Analysis, Proceedings
of the 10th Water Reactor Safety Information Meeting, Gaithersburg,
MD, October 1982.
S. R. Greene, W. A. Condon, and H.
L. Dodds Jr., Investigation of Drywell
Flooding at the Browns Ferry Nuclear Plant, American Nuclear Society Summer
Meeting, Los Angeles, CA, June 1982.
D. H. Cook, R. M. Harrington, S.
R. Greene, S. A. Hodge, and D. D. Yue, Station
Blackout at Browns Ferry Unit One – Accident Sequence Analysis,
NUREG/CR-2182, ORNL/NUREG/TM-455/V1, Oak Ridge National Laboratory, November
1981.
S. R. Greene, The Design, Implementation and Cost-Benefit Analysis of a Dynamic
Testing Program in the Experimental Breeder Reactor-II, Master’s Thesis,
University of Tennessee, March 1979.
Advanced Reactors
S. R. Greene, SmATHR – the Small Modular Advanced High Temperature Reactor, Infocast
2011 SMR Symposium, Washington, D.C., March 28, 2011.
S. R. Greene, J. C. Gehin, D. E.
Holcomb, et al., Pre-Conceptual Design of
a Fluoride-Salt Cooled Small Modular Advanced High-Temperature Reactor (SmAHTR),
ORNL/TM-2010/199, Oak Ridge National Laboratory, December 2010.
Danut Ilas, Jess C. Gehin,
Sherrell R. Greene, Preliminary Nuclear
Design Studies for a Small Modular Advanced High-Temperature Reactor (SmAHTR),
American Nuclear Society 2010 Winter Meeting, Las Vegas, NV, November 7-11,
2010.
Juan J. Carbajo, Graydon L. Yoder,
Sherrell R. Greene, Transient
Thermal-Hydraulic Simulation of the Small Modular Advanced High-Temperature
Reactor (SmAHTR), American Nuclear Society 2010 Winter Meeting, Las Vegas,
NV, November 7-11, 2010.
Sherrell R. Greene, SmAHTR – A Small Modular High-Temperature
Reactor, Transactions of the American Nuclear Society, Volume 103, 2010
Winter Meeting, Las Vegas, NV, November 7-11, 2010.
Sherrell R. Greene, David E.
Holcomb, Jess C. Gehin, et al., SMAHTR –
A Concept for a Small, Modular Advanced High Temperature Reactor, Paper
205, Proceedings of HTR-2010, Prague, Czech Republic, October 18-20, 2010.
S. R. Greene, SmAHTR – the Small Modular Advanced High Temperature Reactor,
presentation to Department of Energy, Fluoride Salt High Temperature Reactor
Workshop, Oak Ridge National Laboratory, September 20-21, 2010.
S. R. Greene, SmAHTR – the Small Modular Advanced High Temperature Reactor, 4th
Annual Asia-Pacific Nuclear Energy Forum, Berkeley, CA, June 18, 2010, http://bnrc.berkeley.edu/documents/forum-2010/Presentations/F-Session-II-P/Sherrell_Greene_ORNL_Pres.pdf.
S. R. Greene, Fluoride Salt Reactors (FHRs) and the Five Imperatives of Nuclear
Energy, Proceedings of the American Nuclear Society Annual Meeting, San
Diego, CA, June 2010.
S. R. Greene, Centurion Reactors – Achieving Commercial Power Reactors with 100+ Year
Operating Lifetimes, American Nuclear Society Winter Meeting, Washington,
DC, November 2009.
J. C. Cleveland and S. R. Greene, Application of THERMIX-KONVEK Code to
Accident Analysis of Modular Pebble Bed High Temperature Reactors (HTRs),
NUREG/CR-4694, ORNL/TM 9905, Oak Ridge National Laboratory, Oak Ridge, TN,
August 1986.
J. C. Cleveland and S. R. Greene, Application of THERMIX-KONVEK Code to
Accident Analyses of Modular Pebble Bed HTRs, ORNL/TM-9905, Oak Ridge
National Laboratory, December 1985.
Space Reactors
S. R. Greene, Lessons Learned (?) from 50 Years for U.S. Space Fission Power
Development, Paper 1074, Proceedings of the Space Nuclear Conference 2005,
American Nuclear Society Annual Meeting, San Diego, CA, June 5-9, 2005.
Louis Qualls, Sherrell R. Greene,
Edward Blakeman, Ken W. Childes, PRESTO:
Power Reactor for Surface Terminal Operation, Paper 1201, Proceedings of
the Space Nuclear Conference 2005, San Diego, CA, June 5-9, 2005.
S. R. Greene et al., Moving Out! – An Integrated Research,
Development, and Demonstration Plan (IRDDP) for Space Power and Propulsion
Reactor Technology, ORNL/TM-2004/219, Oak Ridge National Laboratory,
November 2004.
A.
L. Qualls and S. R. Greene, PRESTO: Power Reactor for Surface Terminal
Operations Conceptual Point Design, ORNL/LTR/SRTP/04-13, Oak Ridge National
Laboratory, July 2004.
S. R. Greene, Space Fission Power
Technology Integrated Research, Development, and Demonstration Plan (IRDDP)
Overview, Space Fission Power Programs Review, Albuquerque, NM, July 2004.
S. R. Greene, A. L. Qualls, J. C.
Gehin, and E. D. Blakeman, Feasibility
Study of the PRESTO Boiling Liquid-Metal/Stirling Engine Power Reactor Concept
for Lunar and Martian Surface Applications, ORNL/LTR/SRTP/04-10, Oak Ridge
National Laboratory, April 2004.
S.
H. Kimm, A. L. Qualls, Sherrell R. Greene, Jeffrey O. Johnson, Development of Optimization Methodology for
Space Reactor Power System Design, Space Technology and Applications International
Forum – STAIF-2004, AIP Conference Proceedings, Vol. 699, Albuquerque NM,
February 2004.
M. L. Tinker, A. L. Qualls, Sherrell Greene, et al, Nuclear Electric Vehicle Optimization Toolset (NEVOT): Integrated
System Design Using Genetic Algorithms, Space Technology and Applications
International Forum – STAIF-2004, AIP Conference Proceedings, Vol. 699,
Albuquerque NM, February 2004.
A.
L. Qualls, E. D. Blakeman, S. R. Greene, et al., Optimization of Space Reactor Power systems Using Genetic Algorithms,
Space Technology and Applications International Forum – STAIF-2004, AIP
Conference Proceedings, Vol. 699, Albuquerque NM, February 2004.
Sherrell
R. Greene, A. L. Qualls, PRESTO – A
Simple, Compact, Fission Power System For Mars Surface Power Applications,
Space Technology and Applications International Forum – STAIF-2004, AIP
Conference Proceedings, Vol. 699, Albuquerque NM, February 2004.
S. R. Greene et al., Summary of an Interagency NASA/DOE Review of
Space Reactor Power System Concepts, ORNL/SR/LTR-2003/001, Oak Ridge
National Laboratory, July 2003.
Reactor-Based
Plutonium Disposition, Mixed-Oxide (MOX) Fuel Cycles, and Non-Proliferation
M. D. Laughter, C.
E. Romano, S. R. Greene et al., Recommendations
for Development of an Integrated Nuclear Fuel Cycle Nonproliferation Strategy,
ORNL/NTPO/LTR-2010-01, Oak Ridge National Laboratory, March 2010.
S. R. Greene, Reactor-Based Plutonium Disposition: Opportunities, Options, and Issues,
International Symposium on MOX Fuel Cycle Technologies for Medium and Long-term
Deployment: Experience, Advances, Trends, ORNL/CP-102975, Vienna, Austria, July
17, 1999.
B. B. Bevard and
S. R. Greene, The Thermal Water
Reactor-Based Plutonium Disposition Project, VOLGA ’97, Moscow, Russia,
Sept. 2, 1997.
S. R. Greene, B.
Bevard et al., FMDP Reactor Alternative
Summary Report, Vol. 1-Existing LWR Alternative, ORNL/TM-13275/V1, Oak
Ridge National Laboratory, September 1996.
S. R. Greene, D.
J. Spellman et al., FMDP Reactor
Alternative Summary Report, Vol. 2-CANDU Heavy Water Reactor Alternative,
ORNL/TM-13275/V2, Oak Ridge National Laboratory, September 1996.
S. R. Greene, S.
E. Fisher et al., FMDP Reactor
Alternative Summary Report, Vol. 3-Partially Complete LWR Alternative,
ORNL/TM-13275/V3, Oak Ridge National Laboratory, September 1996.
S. R. Greene, D.
G. O’Connor et al., FMDP Reactor
Alternative Summary Report, Vol. 4-Evolutionary LWR Alternative,
ORNL/TM-13275/V4, Oak Ridge National Laboratory, September 1996.
B. B. Bevard, S.
R. Greene, et al., Water Reactors Report
for the Joint U.S./Russian Plutonium Disposition Study, Rev. 1,
ORNL/MD/LTR-46, Oak Ridge National Laboratory, 1993.
B. B. Bevard, S.
R. Greene, et al., U.S. Water Reactors
Co-Chair Report for the Joint U.S.
Russian Plutonium Disposition Study, Rev. O., ORNL/MD/LTR-33, Oak
Ridge National Laboratory, 1993.
B. B. Bevard and
S. R. Greene, U.S. Water Reactors
Co-Chair Report for the Joint U.S./Russian Plutonium Disposition Study, Rev. 0,
ORNL/MD/LTR-31, Oak Ridge National Laboratory, 1993.
