T. M. Evans, S. W. Mosher, and S. Slattery, “A Monte Carlo Synthetic-Acceleration Method for Solving the Thermal Radiation Diffusion Equation,” Journal of Computational Physics 258, pp. 338-358 (2014).
J. C. Wagner, D. E. Peplow, and S. W. Mosher, “FW-CADIS Method for Global and Semi-Global Variance Reduction of Monte Carlo Radiation Transport Calculations,” Nuclear Science and Engineering 176, pp. 37-57 (2014).
G. L. Yoder, Jr., et al., “An Experimental Test Facility to Support Development of the Fluoride Salt Cooled High Temperature Reactor,” Annals of Nuclear Energy 64, p. 511 (2014).
L. J. Ott, K. R. Robb, and D. Wang, “Preliminary Assessment of ATFs on LWR During Normal Operation and Under DB and BDB Accident Conditions,” Journal of Nuclear Materials, p. 100 (2014).
J. McFarlane et al., "Performance of a Thermally Stable Polyaromatic Hydrocarbon in a Simulated Concentrating Solar Power Loop," AIMS Energy 2, pp. 41-70 (2014).
J. L. Peterson and J. C. Wagner, "Characteristics of Commercial Spent Nuclear Fuel: Distributed, Diverse, and Changing with Time," RadWaste Solutions 21, pp. 50-59 (2014).
G. Ilas and I. C. Gauld, "Validation of ORIGEN for LWR Used Fuel Decay Heat Analysis with SCALE," Nuclear Engineering and Design 273, pp. 58-67 (2014).
C. A. Gentry et al., "An Investigation of the Use of Fully Ceramic Microencapsulated Fuel for Transuranic Waste Recycling in Pressurized Water Reactors," Nuclear Technology 186(1), pp. 60-75 (2014).
S. J. Zinkle, K. A. Terrani, J. C. Gehin, L. J. Ott, and L. L. Snead, "Accident Tolerant Fuels for LWRs: A Perspective," Journal of Nuclear Materials 448, 374-379 (2014).
M. Farmer, L. Leibowitz, K. A. Terrani, and K. R. Robb, "Scoping Assessments of ATF Impact on Late Stage Accident Progression Including Molten Core-Concrete Interaction," Journal of Nuclear Materials 448, 534-540 (2014).
K. A. Terrani, D. Wang, L. J. Ott, and R. Montgomery, "The effect of fuel thermal conductivity on the behavior of LWR cores during loss of coolant accidents," Journal of Nuclear Materials 448, 512-519 (2014).
R. E. Hale et al., "Dynamic Modeling of Small Modular Nuclear Reactors using MoDSIM," ASME 2014 Small Modular Reactors Symposium, Washington, D.C., April 15-17, 2014.
M.S. Cetiner, D.L. Fugate, R.A. Kisner, M.D. Muhlheim, and R.T. Wood, “Development of A Supervisory Control System Concept for Advanced Small Modular Reactors,” ASME 2014 Small Modular Reactor Symposium, Washington, D.C., April 15-17, 2014.
M. S. Cetiner, "Development of a Supervisory Control System for Advanced Small Modular Reactor," ASME 2014 Small Modular Reactors Symposium, Washington, D.C., April 15-17, 2014.
S. R. Slattery, T. M. Evans, and S. P. Hamilton, "Multilevel Monte Carlo Solvers for Linear Systems," 13th Copper Mountain Conference on Iterative Methods, Copper Mountain, CO, April 6-11, 2014.
G. L. Yoder, Jr., "Examination of Liquid Fluoride Salt Heat Transfer," International Congress on Advances in Nuclear Power Plants, Charlotte, NC, April 6-9, 2014.
D. E. Holcomb, "FHR Technology Development and Demonstration Roadmap," International Congress on Advances in Nuclear Power Plants, Charlotte, NC, April 6-9, 2014.
R. Devoe, K. Banerjee, and R. A. Lefebvre, "Automated Dry-Cask Storage Criticality Analysis Using CSAS6 Templates," ANS Student Conference, State College, Pa., April 3-6, 2014.
J. Hu, I. C. Gauld, J. Banfield, and S. Skutnik, Developing Spent Fuel Assembly for Advanced NDA Instrument Calibration - NGSI Spent Fuel Project, ORNL/TM-2013/576, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2014.
K. R. Robb, M. Farmer, and M. W. Francis, "Ex-Vessel Core Melt Modeling Comparison between MELTSPREAD-CORQUENCH and MELCOR 2.1," ORNL/TM-2014/1, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2014.
T. J. Harrison, "Natural Gas and Nuclear Power: Present Realities and Future Possibilities," 4th Annual Small Modular Reactor Conference, Charlotte, NC, March 31-April 1, 2014.
J. M. Scaglione, K. Banerjee, R. L. Howard, and E. M. Pierce, "Impacts of Groundwater Ionic Species on Spent Fuel," American Chemical Society National Meeting, Dallas, Tex., March 16-20, 2014.
J. M. Scaglione et al., "Integrated Data and Analysis System for Commercial Used Nuclear Fuel Safety Assessments - 14657a," WM2014 Symposium, Phoenix, Ariz., March 2-6, 2014.
J. M. Scaglione, "Used Nuclear Fuel-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS)," WM2014 Symposium, Phoenix, Ariz., March 2-6, 2014.
J. J. Jarrell and D. A. White, "Centralized Used Fuel Resource for Information Exchange - I4656," WM2014 Symposium, Phoenix, Ariz., March 2-6, 2014.
J. J. Jarrell, "WM 2014 CURIE," WM2014 Symposium, Phoenix, Ariz., March 2-6, 2014.
S. M. Bowman et al., Safety and Regulatory Issues of the Thorium Fuel Cycle, ORNL/TM-2013/543, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2014.
B. G. Schnitzler, "Overview of Nuclear Thermal Propulsion Engine Modeling and Design Activities at Oak Ridge National Laboratory," ANS Aerospace Nuclear Science and Technology Division, Slidell, Miss., February 23-28, 2014.
A. L. Qualls and B. G. Schnitzler, "Fuel Development Efforts for Nuclear Thermal Propulsion Within the Department of Energy," Nuclear and Emerging Technologies for Space (NETS) 2014, Stennis Space Center, Miss., February 24-26, 2014.
A. Worrall, "ORNL Measurement of Plutonium in Bulk-Handling Facilities," Inaugural Meeting of US/Japan Plutonium Management Experts Group, Tokyo, Japan, January 27-29, 2014.
J. C. Wagner, "Nuclear Fuels Storage and Transportation Planning Project (NFST) Overview," Institute for Nuclear Materials Management XXIX Spent Fuel Management Seminar (INMM), Arlington, Va., January 13-15, 2014.