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National Laboratory Reports on FHRs

2016

  1. Fluoride Salt-Cooled High-Temperature Demonstration Reactor Point Design, ORNL/TM-2016/85, A. Qualls, N. Brown, B. Betzler, J. Carbajo, M. Greenwood, R. Hale, T. Harrison, J. Powers, K. Robb, J. Terrell, A. Wysocki, February 2016

2015

  1. Preliminary Demonstration Reactor Point Design for the Fluoride Salt-Cooled High-Temperature Reactor, ORNL/TM-2015/700, A. Qualls, B. Betzler, N. Brown, J. Carbajo, M. Greenwood, R. Hale, T. Harrison, J. Powers, K. Robb, J. Terrell, November 2015

2014

  1. Small, Modular Advanced High-Temperature Reactor–Carbonate Thermochemical Cycle, ORNL/TM-2014/88, D. E. Holcomb, D. Ilas, B. Middleton, and M. Arrieta, March 2014.
  2. Small, Modular Advanced High-Temperature Reactor—Carbonate Thermochemical Cycle Technology Readiness Level Assessment, ORNL/TM-2014/69, D. E. Holcomb, March 2014.
  3. Advanced High Temperature Reactor Thermal Hydraulics Analysis and Salt Clean-up System Description, ORNL/TM-2014/499, G. L. Yoder, Andrew Bopp, David Holcomb, David Pointer, and Dean Wang, September 2014.
  4. Update on Small Modular Reactors Dynamic System Modeling Tool – Molten Salt-Cooled Architecture, ORNL/TM-2014/322, Richard Hale, Sacit Cetiner, David Fugate, A. Louis Qualls, Ethan Chaleff, Doug Rogerson, Robert Borum, John Batteh, and Michael Tiller, August 2014 .
  5. Liquid Fluoride Salt Experimentation Using a Small Natural Circulation Cell, ORNL/TM-2014/56, G. L. Yoder, Jr., et al., April 2014.

2013

  1. Fluoride Salt-Cooled High-Temperature Reactor Technology Development and Demonstration Roadmap, ORNL/TM-2013/401, David E. Holcomb, George F. Flanagan, Gary T. Mays, W. David Pointer, Kevin R. Robb, and Graydon L. Yoder, Jr., September 2013.
  2. Preliminary Scaling and controls Analysis of an FHR-HTSE System Idaho National Laboratory Summer 2013 Final Report, INL/EXT-13-29961, Revision 1, Rohit Upadhya, Shannon Bragg-Sitton, and Piyush Sabharwall.
  3. Tritium Formation and Mitigation in High-Temperature Reactor Systems, INL/EXT-12-26758, Revision 2, Hans A. Schmutz, Piyush Sabharwall, and Carl Stoots, March 2013.
  4. Engineering Database of Liquid Salt Thermophysical and Thermochemical Properties, INL/EXT-10-18297, Revision 1, Manohar S. Sohal, Matthias A. Ebner, Piyush Sabharwall, and Phil Sharpe, June 2013.

2012

  1. High-Temperature Fluoride Salt Test Loop, ORNL/TM-2012/430, Graydon L. Yoder, Jr., Adam Aaron, Burns Cunningham, David Fugate, David Holcomb, Roger Kisner, Fred Peretz, Kevin Robb, Dane Wilson, December 2015.
  2. AHTR Mechanical, Structural, and Neutronic Preconceptual Design, ORNL/TM-2012/320, V. K. Varma, D. E. Holcomb, F. J. Peretz, E. C. Bradley, D. Ilas, A. L. Qualls, N. M. Zaharia, September 2012.
  3. AHTR Refueling Systems and Process Description, ORNL/TM-2012/292, V. K. Varma, D. E. Holcomb, E. C. Bradley, N. M. Zaharia, and E. J. Cooper, July 2012.
  4. Advanced High-Temperature Reactor Dynamic System Model Development: April 2012 Status, ORNL/TM-2012/174, A. L. Qualls, M. S. Cetiner, and T. L. Wilson, Jr., April 2012.
  5. Diffusion Welding of Alloys for Molten Salt Service – Status Report, INL/EXT-12-24589, Revision 1, Denis Clark, Ronald Mizia, and Piyush Sabharwall, September 2012.
  6. Thermodynamic Assessment of Hot Corrosion Mechanisms of Superalloys Hastelloy N and Haynes 242 in Eutectic Mixture of Molten Salts KF and ZrF4, INL/EXT-12-24617, Michael V. Glazoff, February 2012.
  7. Technology Development Roadmap for the Advanced High Temperature Reactor Secondary Heat Exchanger, INL/EXT-12-26219, Piyush Sabharwall, John Collins, Denis Clark, Ali Siahpush, William Phoenix, Michael McKellar, and Michael Patterson, September 2012.
  8. FHR Generic Design Criteria, ORNL/TM-2012/226, G. F. Flanagan, D. E. Holcomb, and M. S. Cetiner, June 2012.

2011

  1. Core and Refueling Design Studies for the Advanced High Temperature Reactor, ORNL/TM-2011/365, D. E. Holcomb, D. Ilas, V. K. Varma, A. T. Cisneros, R. P. Kelly, and J. C. Gehin, September 2011.
  2. Vortex Diode Analysis and Testing for Fluoride Salt-Cooled High-Temperature Reactors, ORNL/TM-2011/425, Graydon L. Yoder, Jr., Yousri Elkassabgi, Gerardo De Leon, Catlin Fetterly, Jorge Ramos, James Robbins, and R. Burns Cunningham, September 2011.
  3. Advanced High Temperature Reactor Systems and Economic Analysis, ORNL/TM-2011/364, D. E. Holcomb, F. J. Peretz, and A. L. Qualls, September 2011.
  4. Feasibility Study of Secondary Heat Exchanger Concepts for the Advanced High Temperature Reactor, INL/EXT-11-23076, Piyush Sabharwall, Eung Soo Kim, Ali Siahpush, Nolan Anderson, Michael Glazoff, Bill Phoenix, Ron Mizia, Denis Clark, Mike McKellar, and M.W. Patterson, September 2011.
  5. Process Heat Exchanger Options for the Advanced High Temperature Reactor, INL/EXT-11-21584, Piyush Sabharwall, Eung Soo Kim, Michael McKellar, and Nolan Anderson, June 2011.
  6. Cladding Alloys for Fluoride Salt Compatibility, ORNL/TM-2011/95, Govindarajan Muralidharan, Dane F. Wilson, Larry R. Walker, Michael L. Santella, and David E. Holcomb, May 2011.

2010

  1. An Overview of Liquid Fluoride Salt Heat Transport Systems, ORNL/TM-2010/156, D. E. Holcomb, and M. S. Cetiner, September 2010.
  2. Conceptual Design of Forced Convection Molten Salt Heat Transfer Testing Loop, INL/EXT-10-19908, Manohar S. Sohal, Piyush Sabharwall, Pattrick Calderoni, Alan K. Wertsching, Brandon S. Grover, and Phil Sharpe, September 2010.
  3. An Experimental Test Plan for the Characterization of Molten Salt Thermochemical Properties in Heat Transport Systems, INL/EXT-10-19921, Pattrick Calderoni, September 2010.
  4. Molten Salts for High Temperature Reactors: University of Wisconsin Molten Salt Corrosion and Flow Loop Experiments – Issues Identified and Path Forward, INL/EXT-10-18090, Piyush Sabharwall, Matt Ebner, Manohar Sohal, Phil Sharpe, Mark Anderson, Kumar Sridharan, James Ambrosek, Luke Olson, and Paul Brooks, March 2010.
  5. Enhanced Molten Salt Purification by Electrochemical Methods: Feasibility Experiments with Flibe, INL/EXT-10-19963, Alan K Wertsching; Brandon S Grover; Pattrick Calderoni, September 2010.
  6. Assessment of the Use of Nitrogen Trifluoride for Purifying Coolant and Heat Transfer Salts in the Fluoride Salt-Cooled High-Temperature Reactor, PNNL-19793, Randall D. Scheele and Andrew M. Casella, September 2010.
  7. Pre-Conceptual Design of a Fluoride- Salt-Cooled Small Modular Advanced High-Temperature Reactor (SmAHTR), ORNL/TM-2010/199, S. R. Greene, J. C. Gehin, D. E. Holcomb, J. J. Carbajo, D. Ilas, A. T. Cisneros, V. K. Varma, W. R. Corwin, D. F. Wilson, G. L. Yoder Jr., A. L. Qualls, F. J. Peretz, G. F. Flanagan, D. A. Clayton, E. C. Bradley, G. L. Bell, J. D. Hunn, P. J. Pappano, and M. S. Cetiner, December 2010.

2009

  1. An Analysis of Testing Requirements for Fluoride Salt Cooled High Temperature Reactor Components, ORNL/TM-2009/297, David E. Holcomb, Sacit M. Cetiner, George F. Flanagan, Fred J. Peretz, and Graydon L. Yoder, Jr., November 2009.

2007

  1. Assessment of Silicon Carbide Composites for Advanced Salt-Cooled Reactors, ORNL/TM-2007/168, Revision 1, Y. Katoh, D.F. Wilson, and C.W. Forsberg, September 2007.
  2. Trade Studies for the Liquid-Salt-Cooled Very High-Temperature Reactor: Fiscal Year 2006 Progress Report, ORNL/TM-2006/140, D. T. Ingersoll, C. W. Forsberg, and P. E. MacDonald, February 2007.

2006

  1. Assessment of Candidate Molten Salt Coolants for the Advanced High-Temperature Reactor (AHTR), ORNL/TM-2006/12, D. F. Williams, L. M. Toth, and K. T. Clarno, March 2006.
  2. Assessment of Candidate Molten Salt Coolants for the NGNP/NHI Heat-Transfer Loop, ORNL/TM-2006/69, D. F. Williams, June 2006.
  3. Additional Physical Property Measurements and Assessment of Salt Compositions Proposed for the Intermediate Heat Transfer Loop, ORNL/GEN4/LTR-06-033, David F. Williams, September 2006.
  4. Neutronic Assessment of Stringer Fuel Assembly Design for Liquid-Salt-Cooled Very High Temperature Reactor (LS-VHTR), ANL-GenIV-074, F. J. Szakaly, T. K. Kim, and T. A. Taiwo, August 2006.
  5. Liquid Salt – Very High Temperature Reactor: Survey of Sodium-cooled Fast Reactor Fuel Handling Systems for Relevant Design and Operating Characteristics, ANL-GenIV-069, J.E. Cahalan and T.A. Taiwo, March 2006.
  6. Refueling Options and Considerations for Liquid-Salt-Cooled Very High-Temperature Reactors, ORNL/TM-2006/92, C. W. Forsberg, June 2006.

2005

  1. Preliminary Neutronic Studies for the Liquid-Salt-Cooled Very High Temperature Reactor (LS-VHTR), ANL-GenIV-052, T. K. Kim, T. A. Taiwo, and W .S. Yang, August 2005.
  2. Status of Physics and Safety Analyses for the Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR), ORNL/TM-2005/218, D. T. Ingersoll, December 2005.
  3. Chemical Considerations for the Selection of the Coolant for the Advanced High-Temperature Reactor, ORNL/GEN4/LTR-05-011, D. F. Williams and L. M. Toth, September 2005.
  4. Initial Study of Decay Heat Removal Systems Performance for the Liquid Salt-Cooled – Very High Temperature Reactor (LS-VHTR), ANL-GenIV-067, James E. Cahalan, James J. Sienicki, Anton Moisseytsev, Mitchell T. Farmer, Floyd E. Dunn, Aleksandar Milicevic, and Yaroslav D. Bodnar, September 2005.
  5. Implementation of Molten Salt Properties into RELAP5-3D/ATHENA, INEEL/EXT-05-02658, Cliff B. Davis, January 2005.

2004

  1. Status of Preconceptual Design of the Advanced High-Temperature Reactor (AHTR), ORNL/TM-2004/104, D. T. Ingersoll, C. W. Forsberg, L. J. Ott, D. F. Williams, J. P. Renier, D. F. Wilson, S. J. Ball, L. Reid, W. R. Corwin, and G. D. Del Cul, May 2004.

MISCELLANEOUS ADDITIONAL PUBLICATIONS

Anselmo T. Cisneros and Dan Ilas, “Neutronics and Depletion Methods for Multibatch Fluoride Salt-Cooled High-Temperature Reactors with Slab Fuel Geometry,” Nuclear Technology 183(3), 331–340 (2013).

Ryan Kelly and Dan Ilas, “Verification of a Depletion Method in Scale for the Advanced High-Temperature Reactor,” Nuclear Technology 183(3), 391–397 (2013).

D. E. Holcomb, “Current Status of Fluoride Salt Cooled High Temperature Reactor R&D Activities in the U.S.,” Conference on Molten Salts in Nuclear Technology (CMSNT-2013), Mumbai, India, Jan. 9–11, 2013.

J. J. Powers, T. J. Harrison, and J. C. Gehin, “A New Approach for Modeling and Analysis of Molten Salt Reactors Using SCALE,” Proc. Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science & Engineering (M&C 2013), Sun Valley, Idaho, May 5–9, 2013.

J. J. Powers, T. J. Harrison, and J. C. Gehin, “Modeling and Analysis of Molten Salt Reactors Using SCALE,” Proc. Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science & Engineering (M&C 2013), Sun Valley, Idaho, May 5–9, 2013.

D. E. Holcomb, “Current Status of Fluoride Salt Cooled High-Temperature Reactor R&D Activities in the U.S.,” Molten Salt and Thorium Reactor Symposium, Shizuoka, Japan, May 16–17, 2013.

D. E. Holcomb and V. K. Varma, “Instrumentation & Control Technologies for Refueling the AHTR,” 8th Int. Conf. on Nuclear Plant Instrumentation, Control and Human–Machine Interface Technologies (NPIC & HMIT), San Diego, Calif., July 22–26, 2012.

D. E. Holcomb et al., “Current Status of the Advanced High Temperature Reactor,” 2012 American Nuclear Society Annual Meeting, Chicago, Ill., June 24–28, 2012.

D. E. Holcomb, “Fluoride Salt Cooled High Temperature Reactors,” PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., Apr. 15–20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill., 2012.

R. Kelly and D. Ilas, “Verification of a Depletion Method in SCALE for the Advanced High Temperature Reactor,” PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., Apr. 15–20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill., 2012.

A. T. Cisneros and D. Ilas, “Neutronics and Depletion Methods for Parametric Studies of Fluoride Salt Cooled High Temperature Reactors with Slab Fuel Geometry and Multi-Batch Fuel Management Schemes,” PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., Apr. 15–20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill., 2012.

D. Ilas, “Neutronics of Prismatic Fluoride Salt Cooled High Temperature Reactors,” PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., Apr. 15–20, 2012, on CD-ROM, American Nuclear Society, LaGrangre Park, Ill., 2012.

D. Ilas, D. E. Holcomb, and V. K. Varma, “Advanced High Temperature Reactor Neutronic Core Design,” PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., Apr. 15–20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill., 2012.

D. E. Holcomb et al., “Current Status of the Advanced High Temperature Reactor,” Proc. 2012 Int. Congress on Advances in Nuclear Power Plants (ICAPP '12), Chicago, Ill., June 24–28, 2012.

G. L. Yoder et al., “An Experiment to Study Pebble Bed Liquid-Fluoride-Salt Heat Transfer,” Proc. ICAPP 2011, Nice, France, May 2–5, 2011.

W. Ren, G. Muralidharan, D. F. Wilson, and D. E. Holcomb, “Considerations of Alloy N for Fluoride Salt-Cooled High-Temperature Reactor Applications,” ASME 2011 Pressure Vessels & Piping Division Conference, Baltimore, Md., July 17–19, 2011.

D. E. Holcomb and J. Uhlir, “Collaborative Project on Fluoride Salt Cooled High Temperature Reactor Technology Development,” Transatlantic Nuclear Days, Int. Conf. on Global Cooperation for Future Development of Nuclear Power, Prague, Czech Republic, Oct. 6–7, 2011.

J. J. Carbajo, G. L. Yoder, and S. R. Greene, “Transient Thermal-Hydraulic Simulation of the Small Modular Advanced High-Temperature Reactor (SmAHTR),” Trans. Am. Nucl. Soc. 103, 505–507 (2010).

J. J. Carbajo, G. L. Yoder, Jr., and S. R. Greene, “Transient Thermal-Hydraulic Simulation of the Small modular Advanced High-Temperature Reactor (SmAHTR),” Proc. 19th Topical Meeting on the Technology of Fusion Energy, Las Vegas, Nev., Nov. 7–11, 2010.

A. T. Cisneros and A. L. Qualls, “Power Conversion Systems for ORNL SmAHTR Fluoride Salt Reactor Conceptual Design,” Proc. 19th Topical Meeting on the Technology of Fusion Energy, Las Vegas, Nev., Nov. 7–11, 2010.

D. Ilas, J. C. Gehin and S. R. Greene, “Preliminary Nuclear Design Studies for a Small Modular Advanced High Temperature Reactor (SmAHTR),” Trans. Am. Nucl. Soc. 103, 607–608 (2010).

G. L. Yoder Jr. et al., “Development of a Forced-Convection Liquid-Fluoride-Salt Test Loop,” Proc. Fifth Int. Conf. on High Temperature Reactor Technology HTR 2010, Prague, Czech Republic, Oct. 18–20, 2010.

M. S. Cetiner et al., “Overview of Component Testing Requirements for a Small Fluoride Salt-Cooled High Temperature Reactor,” Proc. 2010 Int. Congress on Advances in Nuclear Power Plants (ICAPP '10), San Diego, Calif., June 13–17, 2010.

M. S. Cetiner et al., “Status on the Identification of Component Testing Requirements for the Advanced High Temperature Reactor,” Proc. 2010 Int. Congress on Advances in Nuclear Power Plants (ICAPP '10), San Diego, Calif., June 13–17, 2010.

J. C. Gehin et al., “SMAHTR - A Concept for a Small, Modular Advanced High Temperature Reactor,” Proc. Fifth Int. Conf. on High Temperature Reactor Technology HTR 2010, Prague, Czech Republic, Oct. 18–20, 2010.

M. S. Cetiner and D. E. Holcomb, “An Overview of Liquid Fluoride Salt Heat Transport Technology,” Proc. Int. Conf. on High Temperature Reactor Technology HTR 2010, Prague, Czech Republic, Oct. 18–20, 2010.

A. L. Qualls and A. T. Cisneros, “Power Conversion Systems for ORNL SmAHTR Fluoride Salt Reactor Conceptual Design,” Trans. Am. Nucl. Soc. 103, 605–606 (2010).

R. A. Kisner and D. E. Holcomb, “Current Status of Instrumentation For a Fluoride Salt Heat Transport Demonstration Loop,” Proc. Seventh American Nuclear Society Int. Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies, Las Vegas, Nev., Nov. 7–11, 2010.

M. S. Cetiner, D. E. Holcomb, and R. A. Kisner, “Instrumentation Requirements for Fluoride Salt Cooled High Temperature Reactors,” Trans. Am. Nucl. Soc. 103, 573–574 (2010).

Juan Ferrada, Jack Collins, Les Dole, Charles Forsberg, M. Jonathan Haire, Rodney Hunt, Ben Lewis, Ray Wymer, and Jennifer L. Ladd-Lively, Carbonate Thermochemical Cycle for the Production of Hydrogen, National Hydrogen Association (NHA) Annual Conference and Hydrogen Expo Columbia, South Carolina, Mar. 30–Apr. 3, 2009.

C. W. Forsberg, “High-Temperature Reactors for Underground Liquid-Fuels Production with Direct Carbon Sequestration,” Proc. ICAPP ’08, Anaheim, Calif., June 8–12, 2008. 

C. W. Forsberg, P. F. Peterson, and R. A. Kochendarfer, “Design Options for the Advanced High-Temperature Reactor,” Proc. ICAPP ’08, Anaheim, Calif., June 8–12, 2008.

C. W. Forsberg and J. C. Conklin, “A Nuclear-Fossil Combined-Cycle Power Plan for Base-Load and Peak Electricity,” American Nuclear Society 2007 Annual Meeting “It’s All About the People: The Future of Nuclear,” Boston, Mass., June 24–28, 2007, Trans. Am. Nucl. Soc. 96, 683–684 (2007).

Juan J. Carbajo, Grady L. Yoder, and Charles W. Forsberg, “RELAP5-3D Model of the Advanced High Temperature Reactor (AHTR),” American Nuclear Society 2007 Annual Meeting “It’s All About the People: The Future of Nuclear,” Boston, MA, June 24–28, 2007, Trans. Am. Nucl. Soc. 96, 797–799 (2007).

J. J. Carbajo, G. L. Yoder, and C. W. Forsberg, “Lumped Parameter Model of the Advanced High-Temperature Reactor (AHTR),” American Nuclear Society 2007 Annual Meeting “It’s All About the People: The Future of Nuclear,” Boston, MA, June 24–28, 2007, Trans. Am. Nucl. Soc. 96, 795–796 (2007).

T. N. Ake, W. J. Anderson, S. A. Gill, R. A. Kochendarfer, and K. O. Stein, Evaluation of the Liquid Salt-Very High Temperature Reactor (LS-VHTR) Concept, Battelle Energy Alliance contract No. 00045559, Areva NP Inc., Lynchburg, VA, September 2007.

            AREVA found no issues that would prevent this reactor from being developed further. For some specific applications, such as urban proximity siting, industrial heat supply and actinide transmutation, the LS-VHTR could have significant advantages over other Generation IV reactor types. However, it is also recognized that significant hurdles still remain, particularly in the area of material compatibility and performance, to deployment of the LS-VHTR as a commercially viable option.

D.F. Williams, “Revival of Halide Salts as High-Temperature Heat-Transfer Media: Key Technical and Scientific Issues,” ECS Transactions 3(35), 441-451, 2007.

L. R. Dole et al., “Carbonate Thermochemical Cycle for the Production of Hydrogen,” DOE Solar-Thermal Water Splitting Program Review Meeting, Denver, Colo., Nov. 15–16, 2007.

C. W. Forsberg, P. F. Peterson, and H. Zhao, “Sustainability and Economics of the Advanced High-Temperature Reactor,” J. Energy Eng. 132(3), 109–115 (2006).

C. W. Forsberg, V. K. Varma, and T. W. Burgess, “Three-Dimensional Imaging and Precision Metrology for Liquid-Salt-Cooled Reactors,” CD-ROM, Proc. 5th Int. Topical Meeting on Nuclear Plant Instrumentation and Controls, and Human Machine Interface Technology, Embedded Topical in American Nuclear Society 2006 Winter Meeting, Albuquerque, N. Mex., Nov. 12–16, 2006.

C. W. Forsberg, “Developments in Molten Salt and Liquid-Salt-Cooled Reactors," Proc.  2006 Int. Congress on Advances in Nuclear Power Plants (ICAPP '06), Reno, Nev., June 4–8, 2006.

C. W. Forsberg, “Alternative Passive Decay-Heat System for the Advanced High-Temperature Reactor,” Proc. 2006 Int. Congress on Advances in Nuclear Power Plants (ICAPP '06), Reno, Nev., June 4–8, 2006.

D. T. Ingersoll and C. W. Forsberg, “Overview and Status of the Advanced High-Temperature Reactor,” Proc. 2006 Int. Congress on Advances in Nuclear Power Plants (ICAPP '06), Reno, Nev., June 4–8, 2006.

C. W. Forsberg, “Fuel Characteristics and Requirements for the Advanced High-Temperature Reactor,” 2006 ANS Annual Meeting, Embedded Topical: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, Reno, Nev., June 4–8, 2006, Trans. Am. Nucl. Soc. 94, 645–647 (2006).

C. W. Forsberg, “Advanced-High-Temperature-Reactor Spent-Fuel Characteristics and Repository Impacts,” Proc. 11th Int. High-Level Radioactive Waste Management Conference (IHLRWM), Las Vegas, Nev., Apr. 30–May 4, 2006.

C. W. Forsberg, “The Advanced High-Temperature Reactor - AHTR,” Chapter XXVI in Status of Innovative Small and Medium Sized Reactor Designs 2005: Reactors with Conventional Refueling Systems, V. V. Kuznetsov (ed.), IAEA-TECDOC-1485, International Atomic Energy Agency, Vienna, 2006.

C. W. Forsberg, “The Advanced High-Temperature Reactor: High-Temperature Fuel, Liquid Salt Coolant, and Liquid-Metal Plant,” Progress in Nuclear Energy 47(1-4) 32–43 (2005).

K. T. Clarno, C. W. Forsberg, and J. C. Gehin, “Physics Analysis of Coolant Voiding in the Advanced High-Temperature Reactor (AHTR),” 2005 ANS Winter Meeting, “Talk About Nuclear Differently: A Good Story Untold,” Washington, D.C., Nov. 13–17, 2005, Trans. Am. Nucl. Soc. 93, 977–980 (2005).

C. W. Forsberg , P. F. Peterson , and D. F. Williams, "Liquid-Salt-Cooling for Advanced High-Temperature Reactors," Proc. 2005 Int. Conf. on Advances in Nuclear Power Plants (ICAPP ’05), Seoul, Korea, May 15–19, 2005, American Nuclear Society, 2005.

C. W. Forsberg , P. F. Peterson, and D. F. Williams, "Practical Aspects of Liquid-Salt-Cooled Fast-Neutron Reactors," Proc. 2005 Int. Conf. on Advances in Nuclear Power Plants (ICAPP ’05), Seoul, Korea, May 15–19, 2005, American Nuclear Society, 2005.

C. W. Forsberg and K. T. Clarno, “The Advanced High-Temperature Reactor (AHTR): Flux Distribution and Dosimetry,” Twelfth Int. Symp. on Reactor Dosimetry, Gatlinburg, Tenn., May 8–13, 2005, to be published in Journal of ASTM International, ASTM, West Conshohocken, Pa.

C. W. Forsberg, “The Longer-Term Option: The Advanced High-Temperature Reactor,” Proc. Next Generation Nuclear Plant Goals and Challenges, Center of Advanced Nuclear Energy Systems, Massachusetts Institute of Technology, Cambridge, Mass., Feb. 23–24, 2005.

D. T. Ingersoll, E. J. Parma, C. W. Forsberg, and J. P. Renier, “Core Physics Characteristics and Issues for the Advanced High-Temperature Reactor (AHTR) Concept,” Workshop on Advanced Reactors with Innovative Fuels (ARWIF-2005), Oak Ridge, Tenn., Feb. 16–18, 2005, Nuclear Science Committee, OECD Nuclear Energy Agency, Paris, France.

C. W. Forsberg, P. F. Peterson, and H. Zhao, “Sustainability, Water, Dry Cooling, and the Advanced High-Temperature Reactor,” 2004 ANS Winter Meeting: “Leadership Toward a Progressive, Integrated Nuclear Community - Going Forward Together,” Washington, D. C., Nov. 14–18, 2004, Trans. Am. Nucl. Soc. 91, 415–417 (2004).

C. W. Forsberg, “The Advanced High-Temperature Reactor: High-Temperature Fuel, Molten Salt Coolant, and Liquid-Metal Plant,” Proc. 1st COE-INIES Int. Symp. (INIES-1), Tokyo Institute of Japan, Tokyo, Japan, Oct. 31–Nov. 4, 2004.

C. W. Forsberg, P. F. Peterson, and L. Ott, “The Advanced High-Temperature Reactor (AHTR) for Producing Hydrogen to Manufacture Liquid Fuels,” Proc. 2004 Americas Nuclear Energy Symposium, Miami Beach, Fla., Oct. 3–6, 2004, American Nuclear Society, La Grange Park, Ill.

S. J. Ball and C. W. Forsberg, “Advanced High-Temperature Reactor (AHTR) Loss-of-Forced Circulation Accidents,” Proc. 2nd Int. Topical Meeting on High-Temperature Reactor Technology (HTR2004), Beijing, China, Sept. 20–24, 2004, International Atomic Energy Agency, Vienna, Austria, 2004.

C. W. Forsberg, P. F. Peterson, and H. Zhao, “An Advanced Molten Salt Reactor Using High-Temperature Reactor Technology,” Proc. 2004 Int. Congress on Advances in Nuclear Power Plants (ICAPP’04), Embedded Topical: 2004 American Nuclear Society Annual Meeting, Pittsburgh, Pa., June 13–17, 2004, American Nuclear Society, La Grange Park, Ill.

C. W. Forsberg, P. F. Peterson, and P. Pickard, “Maximizing Temperatures of Delivered Heat From the Advanced High-Temperature Reactor,” Proc. 2004 Int. Congress on Advances in Nuclear Power Plants (ICAPP’04), Embedded Topical: 2004 American Nuclear Society Annual Meeting, Pittsburgh, Pa., June 13–17, 2004, American Nuclear Society, La Grange Park, Ill., 2004.

C. W. Forsberg and M. A. Feltus, “Fuel Requirements for the Advanced High-Temperature Reactor: Graphite Coated-Particle Fuel and Molten Fluoride Salt Coolant,” Technical Meeting on Current Status and Future Prospects of Gas-Cooled Reactor Fuels, Vienna, Austria, June 7–9, 2004.

C. W. Forsberg, “A Large Low-Pressure Advanced High-Temperature (AHTR),” Proc. 14th Pacific Basin Nuclear Conference, Honolulu, Hawaii, Mar. 21–25, 2004, American Nuclear Society, La Grange Park, Ill., 2004.

Contacts

David Holcomb, HolcombDE@ornl.gov, Salt Reactor Technical Lead

Jess Gehin, GehinJC@ornl.gov, ORNL Reactor Technology Lead

Gary Mays, MaysGT@ornl.gov, Advanced Reactor Systems and Safety Lead