Monday, April 4, 2011

Post # 38: My Publications

Some of you know that I've been in the nuclear energy, science, and technology R&D world for over three decades.  During that time, I've published a number of reports, professional presentations, journal articles, etc.  Here's a "relatively-complete" listing...

Energy Parks and Energy Infrastructure

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.

S. R. Greene, Centurion Reactors – Achieving Commercial Power Reactors with 100+ Year Operating Lifetimes, American Nuclear Society Winter Meeting, Washington, DC, 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: A Historical Perspective On Our Understanding of BWR Severe Accidents and Their Mitigation," Nuclear Technology, 186, 115-138 (2014); http://dx.doi.org/10.13182/NT13-44

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.

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.

4 comments:

  1. Would it be possible to post or send me a copy of your paper “The Role of BWR Secondary Containments In Severe Accident Mitigation: Issues and Insights From Recent Analyses”?

    Thanks for your attention! :)

    ReplyDelete
  2. Yes. I will upload it sometime this week.
    Thanks for asking Ian.

    Sherrell

    ReplyDelete
  3. Do you have the email contact of Dr. Hodge? I would like to talk to him about one of his earlier reports. If so, please email me his contact information (my email: ark8@njit.edu). I would really appreciate it. Thank you!

    ReplyDelete
    Replies
    1. I"m sorry, but I do not have Steve's email address. He retired many years ago...
      Cheers and thanks for reading my blog.

      Delete