Reactor and Nuclear Systems Division

Reactor and Nuclear Systems Division
2012 Publications

B. Riemer et al., "Status of R&D on Mitigating the Effects of Pressure Waves for the Spallation Neutron Source Mercury Target," Journal of Nuclear Materials 431, 160-171 (2012).

L. C. Leal et al., "ORNL Resolved Resonance Covariance Generation for ENDF/B-VII.1," Nuclear Data Sheets, pp. 3502-3519 (2012).

R. T. Wood, "U. S. Department of Energy Instrumentation and Controls Technology Research for Advanced Small Modular Reactors," International Journal on Nuclear Safety and Simulation 3(4), 292-299 (2012).

G. Ilas, I. C. Gauld, and G. Radulescu, "Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE," Annals of Nuclear Energy 46(1), 43-55 (2012).

I. Remec, R. M. Ronningen, and L. Heilbronn, "Benchmarking of Neutron Production of Heavy-Ion Transport Codes," Journal of ASTM International 9(4), 1-12 (2012).

M. T. Pigni, "Measurement of resolved resonances of Th-232(n, gamma) at the n_TOF facility at CERN," Physical Review C 85(6) (2012).

M. T. Pigni, "Resonance neutron-capture cross sections of stable magnesium isotopes and their astrophysical implications," Physical Review C 85(4) (2012).

H. E. Garcia et al., "Integration of facility modeling capabilities for nuclear nonproliferation analysis," Progress in Nuclear Energy 54(1), 96 (2012).

O. A. Omitaomu et al., "Adapting a GIS-Based Multicriteria Decision Analysis Approach for Evaluating New Power Generating Sites," Applied Energy, 120 (2012).

V. Kucukboyaci and W. J. Marshall, "Spent fuel pool storage calculations using the ISOCRIT burnup credit tool," Annals of Nuclear Energy 39(1), 9-14 (2012).

G. Arbanas et al., "Covariance Matrix of a Double-Differential Doppler-broadened Elastic Scattering Cross Section," EPJ Web of Conferences 27, p. 6 (2012).

A. Yankov et al., "A Two-Step Approach to Uncertainty Quantification of Core Simulators," Science and Technology of Nuclear Installations 2012 (2012).

H. Garcia et al., "Integration of facility modeling capabilities for nuclear nonproliferation analysis," Progress in Nuclear Energy 54, 96-111 (2012).

M. T. Pigni, "Neutron-induced fission cross section of Cm-245: New Results from data taken at the time-of-flight facility n_TOF," Physical Review C 85(3) (2012).

M. T. Pigni, "Measurement and resonance analysis of the Np-237 neutron capture cross section," Physical Review C 85(4) (2012).

D. Chandler, G. I. Maldonado, T. Primm, and L. D. Proctor, "Nuclear Transmutations in HFIR's Beryllium Reflector and Their Impact on Reactor Operation and Reflector Disposal," Nuclear Technology 177(3), pp. 395-412 (2012).

K. T. Clarno et al., "The AMP (Advanced MultiPhysics) Nuclear Fuel Performance Code," Nuclear Engineering and Design 252(1), 108-120 (2012).

D. Wang et al., "Study of Fukushima Dai-ichi Nuclear Power Station Unit 4 Spent Fuel Pool," Nuclear Technology, 180 (2012).

R. L. Kozub et al., "Neutron single particle structure in 131Sn and direct neutron capture cross sections," Physical Review Letters, 109(17), 172501 (2012).

J.-A. Wang et al., "Annual Progress Report on U-Frame Test Setup and Bending Fatigue Test for Vibration Integrity Study (Out-of-cell fatigue testing development - Task 2.3)," ORNL/TM-2012/417, Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2012.

Y. Katoh et al., Status of Irradiation Test Preparation Activities for Silicon Carbide Joining and Irradiation Studies, ORNL/TM-2012/597, Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2012.

J. C. Wagner et al., Categorization of Used Nuclear Fuel Inventory in Support of a Comprehensive National Nuclear Fuel Cycle Strategy, ORNL/TM-2012/308, Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2012.

B. J. Ade, SCALE/TRITON Primer: A Primer for Light Water Reactor Lattice Physics Calculations, ORNL/TM-2011/21, Oak Ridge National Laboratory, Oak Ridge, Tenn., November 2012.

C. G. Baker et al., "High Performance Radiation Transport Simulations: Preparing for TITAN," SC12 Supercomputing, Salt Lake City, Utah, November 12-15, 2012.

R. T. Jubin et al., "Impact of Fuel Age on DF Requirements," Proc. 2012 ANS Winter Meeting and Nuclear Technology Expo, San Diego, Calif., November 11-15, 2012.

J. E. Banfield, S. P. Hamilton, K. T. Clarno, and G. I. Maldonado, "A New Semi-Implicit Direct Kinetics Method with Analytical Representation of Delayed Neutrons," Proc. 2012 ANS Winter Meeting and Nuclear Technology Expo, San Diego, Calif., November 11-15, 2012.

S. Goluoglu and C. M. Hopper, "US DOE Nuclear Criticality Safety Engineer Hands-On Subcritical and Critical Experiments Training and Education Course," Proc. 2012 ANS Winter Meeting and Nuclear Technology Expo, San Diego, Calif., November 11-15, 2012.

N. Cantrell et al., "Extending a CAD-Based Cartesian Mesh Generator for the Lattic Boltzmann Method," Proc. 2012 ANS Winter Meeting and Nuclear Technology Expo, San Diego, Calif., November 11-15, 2012.

V. B. Khane, P. K. Jain, and J. D. Freels, "Development of CFD models to support LEU Conversion of ORNL's High Flux Isotope Reactor," Proc. 2012 ANS Winter Meeting and Nuclear Technology Expo, San Diego, Calif., November 11-15, 2012.

D. Wang, "Reduce Numerical Diffusion in TRACE Using the High-Resolution Numerical Method ENO," Proc. 2012 ANS Winter Meeting and Nuclear Technology Expo, San Diego, Calif., November 11-15, 2012.

D. E. Peplow, "Comparison of Mybrid Methods for Global Variance Reduction in Shielding Calculations," Proc. 2012 ANS Winter Meeting and Nuclear Technology Expo, San Diego, Calif., November 11-15, 2012.

K. R. Robb, M. W. Francis, and L. J. Ott, "Fukushima Daiichi Unit 3 MELCOR Investigation," Proc. 2012 ANS Winter Meeting and Nuclear Technology Expo, San Diego, Calif., November 11-15, 2012.

A. M. Ibrahim et al., "Automatic Mesh Adaptivity for Hybrid Monte Carlo/Deterministic Neutronics Modeling of Difficult Shielding Problems," Proc. 2012 ANS Winter Meeting and Nuclear Technology Expo, San Diego, Calif., November 11-15, 2012.

A. S. Joshi et al., "PRATHAM: Parallel Thermal Hydraulics Simulations using Advanced Mesoscopic Methods," Proc. 2012 ANS Winter Meeting and Nuclear Technology Expo, San Diego, Calif., November 11-15, 2012.

C. M. Perfetti and B. T. Rearden, "Data Adjustment Exercises for Fast Reactor Benchmark Problems Using SCALE," Trans. Am. Nucl. Soc., 107, 624-627 (2012).

C. M. Perfetti, "Advanced Methods for Eigenvalue Sensitivity Coefficient Calculations," Trans. Am. Nucl. Soc., 107, 575-578 (2012).

K. S. Kim, "Preliminary Assessment of Resonance Interference Consideration by Using 0-D Slowing Down Calculation in the Embedded Self-Shielding Method," Trans. Am. Nucl. Soc., 107, 1128-1131 (2012).

K. H. Guber, "ORNL Neutron Cross-Section Measurements Activities," Trans. Am. Nucl. Soc., 107, 687-689 (2012).

C. L. Britton, Jr. et al., Johnson Noise Thermometry for Advanced Small Modular Reactors, ORNL/TM-2012/345, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2012.

R. A. Kisner et al., Embedded Sensors and Controls to Improve Component Performance and Reliability: Conceptual Design Report, ORNL/TM-2012/433, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2012.

V. K. Varma et al., AHTR Mechanical, Structural, and Neutronic Preconceptual Design, ORNL/TM-2012/320, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2012.

M. Monterial and V. J. Jodoin, Updated Properties of Fractionated Fallout. Predictions of Activities, Exposure Rates, and Gamma Spectra for Selected Situations, ORNL/TM-2012/481, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2012.

M. L. Baird and D. E. Bernholdt, Initial Experiences with the NEAMS Early User Program, ORNL/TM-2012/476, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2012.

R. T. Wood, "Instrumental and Controls Technology Research Under U. S. Department of Energy Nuclear Power Programs," 14th International Workshop on Nuclear Safety and Simulation (IWNSS2012), Harbin, China, October 23-24, 2012.

J. T. Mihalczo et al., "Fast Neutron Imaging with API DT Neutron Generators," Portable Neutron Generators and Generator-Based Technologies International Conference, Moscow, Russia, October 22-27, 2012.

S. J. Zinkle et al., "Accident Tolerant Fuels for Light Water Reactors," The Nuclear Materials Conference (NuMat 2012), Osaka, Japan, October 21-25, 2012.

R. T. Wood, "Instrumentation, Controls, and Human-Machine Interface Research Under the Advanced Small Modular Reactor Program," Future of Instrumentation International Workshop, Gatlinburg, Tenn., October 8-9, 2012.

V. B. Khane, P. K. Jain, and J. D. Freels, "COMSOL Simulations for Steady State Thermal Hydraulics Analyses of ORNL's High Flux Isotope Reactor (HFIR)," COMSOL 2012, Boston, Mass., October 3-5, 2012.

V. B. Khane, P. K. Jain, and J. D. Freels, "Development of a 3D Production Model in COMSOL for Thermal Hydraulics Analyses of ORNL's High Flux Isotope Reactor," COMSOL 2012, Boston, Mass., October 3-5, 2012.

J. D. Freels, P. K. Jain, and R. W. Hobbs, "Design and Nuclear-Safety Related Simulations of Bare-Pellet Test Irradiations for the Production of Pu-238 in the High Flux Isotope Reactor using COMSOL," COMSOL 2012, Boston, Mass., October 3-5, 2012.

G. L. Bell, Summary of FY12 HFIR Irradiation Testing Activities, ORNL/TM-2012/454, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2012.

S. Zhang et al., "Structures of exotic 131,133Sn isotopes and effect on r-process nucleosynthesis," Physical Review C 86, 1-5, September 2012.

J. M. Scaglione, Initial Assessment of Uncertainties Associated with BADGER Methodology, ORNL/TM-2012/39, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2012.

R. Belles, G. T. Mays, O. A. Omitaomu, and W. P. Poore, Updated Application of Spatial Data Modeling and Geographical Informaiton Systems (GIS) for Identification of Potential Siting Options for Small Modular Reactors, ORNL/TM-2012/403, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2012.

J. McFarlane et al., Ways to Minimize Water Usage in Engineered Geothermal Systems, ORNL/TM-2012/412, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2012.

D. A. Hooper, J. J. Henkel, and M. Whitaker, "Application of Condition-Based Monitoring Techniques for Remote Monitoring of a Simulated Gas Centrifuge Enrichment Plant," 9th International Conference on Facility Operations - Safeguards Interface, Savannah, Ga., September 23-27, 2012.

K. V. Gilligan, A. C. Pederson, and B. L. Kirk, "Human Capital Development and Safeguards at Facilities," 9th International Conference on Facility Operations - Safeguards Interface, Savannah, Ga., September 23-27, 2012.

J. R. Younkin et al., "A Robust and Flexible Design for GCEP Unattended Online Enrichment Monitoring," 9th International Conference on Facility Operations - Safeguards Interface, Savannah, Ga., September 23-27, 2012.

T. D. Burchell et al., "H-451 Graphite Irradiation Creep Data from HFIR Creep Rabbit Experiments," 12th International Graphite Specialist Meeting (INGSM-13), Meitingen, Germany, September 23-26, 2012.

R. H. Howard, J. L. McDuffee, M. A. Fechter, and Y. Katoh, "Development of HFIR Target Experiment for Graphite Irradiation Creep," 12th International Graphite Specialist Meeting (INGSM-13), Meitingen, Germany, September 23-26, 2012.

L. C. Leal et al., "56Fe Resonance Evaluation up to 1.5 MeV," WINS 2012, Boston, Mass., September 17-19, 2012.

M. Rohde, T. L. Huang, and J. A. March-Leuba, "LAPUR6 Benchmark of Stability Data Measured in the Delft University of Technology's GENESIS Loop," Nuclear Thermal Hydraulics and Operation Safety (NUTHOS-9), Kaohsiung, Taiwan, September 9-13, 2012.

H. J. Smith and B. B. Bevard, Core Average (MOX/LEU) Nuclide Ratios for Sequoya and Brown's Ferry Reactors Part 1 - Problem Description, Inputs and Results and Part 2 - SCALE/TRITON Input Models, ORNL/TM-2012/93, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 2012.

P. K. Jain, J. D. Freels, and D. H. Cook, 3D COMSOL Simulations for Thermal Deflection of HFIR Fuel Plate in the "Cheverton-Kelley" Experiments, ORNL/TM-2012/138, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 2012.

W. J. Marshall and J. C. Wagner, Consequences of Fuel Failure on Criticality Safety of Used Nuclear Fuel, ORNL/TM-2012/325, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 2012.

A. Phillippe et al., Analysis of the IFA-432, IFA-597, and IFA-597mox Fuel Performance Experiments by FRAPCON-3.4, ORNL/TM-2012/195, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 2012.

G. Ilas et al., Validation of SCALE for High Temperature Gas-Cooled Reactors Analysis, ORNL/TM-2011/161, NUREG/CR-7107, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 2012.

S. M. McConchie et al., "Active-induced Time Correlation Signatures for the Characterization of Shielded HEU Using D-T Neutron Generators," CAARI 2012, Ft. Worth, Tex., August 5-9, 2012.

J. M. Crye et al., "Active-induced Time Correlation Signatures for the Characterization of Shielded HEU," CAARI 2012, Ft. Worth, Tex., August 5-9, 2012.

V. K. Varma et al., AHTR Refueling Systems and Process Description, ORNL/TM-2012/292, Oak Ridge National Laboratory, Oak Ridge, Tenn., July 2012.

T. J. Harrison and A. L. Qualls, "Power Profile Control in Graphite-Based Nuclear Thermal Propulsion Reactor Cores for Mitigation of Mid-Band Corrosion," 48th AIAA/ASME/SAE/ASEE Joint Propulsion Conference & Exhibit and 10th International Energy Conversion Engineering Conference, Atlanta, Ga., July 29-August 1, 2012.

A. L. Qualls, "Past, Present, and Future of Space Power and Propulsion," 48th AIAA/ASME/SAE/ASEE Joint Propulsion Conference & Exhibit and 10th International Energy Conversion Engineering Conference, Atlanta, Ga., July 29-August 1, 2012.

M. P. Trammell et al., "UC-ZrC Composite Fuel Development at ORNL," 48th AIAA/ASME/SAE/ASEE Joint Propulsion Conference & Exhibit and 10th International Energy Conversion Engineering Conference, Atlanta, Ga., July 29-August 1, 2012.

A. Worrall, "Role of Fuel Cycle Assessment and Decision-Making in the UK," EPRI Nuclear Fuel Cycle Assessment Workshop, Nashville, Tenn., July 24-25, 2012.

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

D. Hardesty et al., "Insights Gained for Updating an Analog I&C System to a Digital System," 8th International Conference on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC & HMIT), San Diego, Calif., July 22-26, 2012.

D. Hardesty et al., "Lessons Learned While Updating NUREG-1537 (Viewgraphs)," 8th International Conference on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC & HMIT), San Diego, Calif., July 22-26, 2012.

M. D. Muhlheim et al., "Insights Gained for Updating an Analog I&C System to a Digital System," 8th International Conference on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC & HMIT), San Diego, Calif., July 22-26, 2012.

M. D. Muhlheim et al., "Lessons Learned While Updating NUREG-1537," 8th International Conference on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC & HMIT), San Diego, Calif., July 22-26, 2012.

F. Becvar et al., "Neutron Resonance Data Exclude Random Matrix Theory," Fortschritte der Physik, pp. 1-15 (2012).

A. L. Swift et al., "Attributes from NMIS Time Coincidence, Fast-Neutron Imaging, Fission Mapping, and Gamma-Ray Spectrometry Data," INMM 53rd Annual Meeting, Orlando, Fla., July 15-19, 2012.

B. R. Grogan and J. T. Mihalczo, "Identification of Lithium Isotopes Using Time-Tagged Neutron Scattering," INMM 53rd Annual Meeting, Orlando, Fla., July 15-19, 2012.

C. F. Weber, "Generalized Modeling of Enrichment Cascades That Include Minor Isotopes," INMM 53rd Annual Meeting, Orlando, Fla., July 15-19, 2012.

S. E. Skutnik et al., "Creating NDA "working standards" through high-fidelity spent fuel modeling,"" INMM 53rd Annual Meeting, Orlando, Fla., July 15-19, 2012.

S. E. Skutnik, M. D. Eipeldauer, and T. E. Margrave, "Innovations in University Nonproliferation Education through a Joint ORNL-NCSU Partnership," INMM 53rd Annual Meeting, Orlando, Fla., July 15-19 2012.

D. A. Hooper et al., "Predictive Fallout Composition Modeling: Improvements and Applications of the Defense Land Fallout Interpretive Code," INMM 53rd Annual Meeting, Orlando, Fla., July 15-19, 2012.

M. Monterial et al., "Automating the Coupling of ORIGEN with GADRAS via the Fallout Analysis Tool for National Technical Nuclear Forensics," INMM 53rd Annual Meeting, Orlando, Fla., July 15-19, 2012.

B. Philip et al., "The Advanced Mutli-Physics (AMP) Package with An Application to Fuel Assemblies in Nuclear Reactors," 2012 SIAM Annual Meeting, Minneapolis, Minn., July 9-13, 2012.

B. Philip et al., "The Advanced Multi-Physics (AMP) Framework with an Application to Nuclear Reactor Simulations," 2012 SIAM Annual Meeting, Minneapolis, Minn., July 9, 2012.

S. J. Ball, T. L. Wilson, Jr., and R. T. Wood, Advanced Control and Protection System Design Methods for Modular HTGRs, ORNL/TM-2012/170, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 2012.

G. F. Flanagan, D. E. Holcomb, and M. S. Cetiner, FHR Generic Design Criteria, ORNL/TM-2012/226, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 2012.

G. T. Mays et al., Application of Spatial Data Modeling Systems, Geographical Information Systems (GIS), and Transportation Routing Optimization Methods for Evaluating Integrated Deployment of Interim Spent Fuel Storage Installations and Advanced Nuclear Plants, ORNL/TM-2012/237, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 2012.

W. J. Marshall and J. C. Wagner, "Impact of Fuel Failure on Criticality Safety of Used Nuclear Fuel," PSAM 11, Helsinki, Finland, June 25-29, 2012.

M. H. Piro et al., "Computational Thermodynamics in the Advanced Multi-Physics Code," 2012 American Nuclear Society Annual Meeting, Chicago, Ill., June 24-28, 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.

J. E. Gunning, et al., "X-ray Backscatter Imaging of Nuclear Fuel Rods," 2012 American Nuclear Society Annual Meeting, Chicago, Ill., June 24-28, 2012.

C. W. Alexander, S. L. Hogle, and G. I. Maldonado, "Development and Comparison of High Flux Isotope Reactor Actinide Target Models," 2012 American Nuclear Society Annual Meeting, Chicago, Ill., June 24-28, 2012.

D. E. Peplow, "Methods for Detector Placement and Analysis fo Criticality Accident Alarm Systems," 2012 American Nuclear Society Annual Meeting, Chicago, Ill., June 24-28, 2012.

J. E. Gunning et al., "X-ray Backscatter Imaging of Nuclear Fuel Rods," 2012 American Nuclear Society Annual Meeting, Chicago, Ill., June 24-28, 2012.

B. Philip et al., "Computational Approach to Nuclear Fuel Assembly Simulation,"2012 American Nuclear Society Annual Meeting, Chicago, Ill., June 24-28, 2012.

C. A. Gentry et al., "Application of Fully Ceramic Microencapsulated Fuels in Light Water Reactors," 2012 American Nuclear Society Annual Meeting, Chicago, Ill., June 24-28, 2012.

N. M. George et al., "Preliminary Evaluation of Burnable Poisons in Uranium-Based Fully Ceramic Microencapsulated Fuel for PWRs," 2012 American Nuclear Society Annual Meeting, Chicago, Ill., June 24-28, 2012.

J. Banfield et al., "Benchmarking of Software and Methods for Use in Transient Multidimensional Fuel Performance with Spatial Reactor Kinetics," ICAPP '12, Chicago, Ill., June 24-28, 2012.

G. Ilas, T. Primm, and D. G. Renfro, "Design of a Low-Enriched Uranium Fuel for the High Flux Isotope Reactor - Reactor Physics Analyses," Trans. Am. Nucl. Soc. 106, 845-848 (2012).

J. J. Carbajo, "MELCOR Sensitivity Study for a PWR Containment," Trans. Am. Nucl. Soc. 106, 552-554 (2012).

J. J. Carbajo, "MELCOR Model of the Spent Fuel Pool of Fukushima Dai-ichi Unit 4," Trans. Am. Nucl. Soc. 106, 549-551 (2012).

L. C. Leal et al., "ORNL Resonance Evaluation for ENDF/B-VII.1," Trans. Am. Nucl. Soc. 106, 784-785 (2012).

A. M. Bevill and S. W. Mosher, "A New Source Biasing Approach in ADVANTG," Trans. Am. Nucl. Soc. 106, 350-353 (2012).

K. T. Clarno et al., "Integrated Radiation Transport and Thermo-Mechanics Simulation of a PWR Assembly," Trans. Am. Nucl. Soc. 106, 726-731 (2012).

S. Goluoglu, K. B. Bekar, and D. Wiarda, "SCALE Continuous-Energy Monte Carlo Depletion with Parallel KENO in TRITON," Trans. Am. Nucl. Soc. 106, 723-725 (2012).

B. T. Rearden and W. J. Marshall, "Examination of Validation Outlier Cases Using the Sensitivity and Uncertainty Analysis Tools of SCALE 6.1," Trans. Am. Nucl. Soc. 106, 461-464 (2012).

D. E. Peplow and L. Wetzel, "Methods for Detector Placement and Analysis of Criticality Accident Alarm Systems," Trans. Am. Nucl. Soc. 106, 497-500 (2012).

W. J. Marshall and B. T. Rearden, "Criticality Safety Validation of SCALE 6.1 with ENDF/B-VII.0 Libraries," Trans. Am. Nucl. Soc. 106, 456-460 (2012).

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

J. McFarlane et al., "Polyaromatic Naphthalene Derivatives as Heat Transfer Fluids," presented at SunShot 2012, Denver, Colo., June 13, 2012.

M. H. Piro et al., "Thermodynamic Equilibrium Calculations in Nuclear Fuel Simulations," presented at Computer Coupling Phase Diagrams and Thermochemistry (CALPHAD), Berkeley, Calif., June 3-8, 2012.

M. H. Piro et al., "Coupling Thermodynamic Computations with Multi-Physics Nuclear Fuel Codes," Computer Coupling Phase Diagrams and Thermochemistry (CALPHAD), Berkeley, Calif., June 3-8, 2012.

J. R. Bell et al., Phenylnaphthalene as a Heat Transfer Fluid for Concentrating Solar Power: High-Temperature Static Experiments, ORNL/TM-2012/118, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2012.

B. T. Rearden, "SCALE Newsletter, Number 44, Spring 2012," Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2012.

S. J. Ball, D. E. Holcomb, and M. S. Cetiner, HTGR Measurements and Instrumentation Systems, ORNL/TM-2012/107, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2012.

E. D. Collins, D. Benker, R. J. Vedder, D. C. Guillermo, and R. J. Ellis, "Scale-up TALSPEAK Demonstrations - Implications for a Single Solvent Extraction Recovery of Am-Cm and Efficient Irradiation/Transmutation," 36th Actinide Separations Conference, Chattanooga, Tenn., May 21-24, 2012.

G. H. Brown et al., "Carborane-Loaded Silicone Rubber and Polystyrene Scintillators for Neutron Detection," IEEE Symposium on Radiation Measurements and Applications, Oakland, Calif., May 14-17, 2012.

J. M. Scaglione and D. Vinson, "Criticality Task Force Meeting -- DOE Data Needs for EST-Criticality Related," NEI Used Fuel Management Conference, St. Petersburg, Fla., May 7, 2012.

S. Goluoglu and C. M. Hopper, "US DOE Nuclear Criticality Safety Engineer Hands-On Subcritical and Critical Experiments Training and Education Course," EFCOG Safety Analysis Workshop 2012, Santa Fe, N. Mex, May 4-10, 2012.

S. Goluoglu and C. M. Hopper, "US DOE NCS Engineer Hands-On Subcritical and Critical Experiments Training and Education Course," EFCOG Safety Analysis Workshop 2012, Santa Fe, N. Mex., May 4-10, 2012.

T. D. Burchell, J. P. Strizak, J. L. McDuffee, and K. R. Thoms, Experimental Plan for HFIR High Temperature Graphite Irradiation Capsule (HTV), ORNL/TM-2011/10, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2012.

G. Radulescu et al., An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses - Isotopic Composition Predictions, ORNL/TM-2011/509, NUREG/CR-7108, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2012.

J. M. Scaglione et al., An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses - Criticality (keff) Predictions, ORNL/TM-2011/514, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2012.

I. C. Gauld, G. Ilas, and B. L. Broadhead, "Application of SCALE for HTR-10 Spent Fuel Safeguards," presented at the China-U.S. PBMR Safeguards Workshop, Beijing, China, April 17-20, 2012.

I. C. Gauld, G. Ilas, and B. L. Broadhead, "ORIGEN Tutorial - Fast, Easy, and Accurate Fuel Depletion, Decay and Source Term Analysis," presented at the China-U.S. PBMR Safeguards Workshop, Beijing, China, April 17-20, 2012.

R. Slaybaugh, T. M. Evans, and G. G. Davidson, and P. Wilson, "Rayleigh Quotient Iteration in 3D, Deterministic Neutron Transport," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

D. E. Holcomb, "Fluoride Salt Cooled High Temperature Reactors," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrangre Park, Ill. (2012)

A. Santamarina et al., "Re-estimation of Nuclear Data and JEFF 3.1.1 Uncertainty Calculations," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrangre Park, Ill. (2012)

S. P. Hamilton et al., "Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrangre 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., April 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., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

S. L. Hogle, G. I. Maldonado, and C. W. Alexander, "The Effects of Flux Spectrum Perturbation on Transmutation of Actinides: Optimizing the Production of Transcurium Isotopes," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 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., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrangre Park, Ill. (2012)

D. Ilas, "SCALE Code Validation for Prismatic High-Temperature Gas-Cooled Reactors," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange 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., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

A. Yankov et al., "Comparison of XSUSA and "Two-Step" Approaches for Full Core Uncertainty Quantification," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrangre Park, Ill. (2012)

A. Yankov et al., "A Generalized Adjoint Approach for Quantifying Reflector Assembly Discontinuity Factor Uncertainties," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

N. George et al., "Neutronics Studies of Uranium-Based Fully Ceramic Micro-Encapsulated Fuel for PWRs," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

A. Ibrahim et al., "Acceleration of Monte Carlo Criticality Calculations Using Deterministic-Based Starting Sources," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

G. Ilas and T. Primm, "Performance and Safety Parameters for the High Flux Isotope Reactor," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

C. McGraw and G. Ilas, "PWR Cross Section Libraries for ORIGEN-ARP," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

M. L. Williams et al., "Development of a Statistical Sampling Method for Uncertainty Analysis with SCALE," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

M. L. Williams and K. S. Kim, "The Embedded Self-Shielding Method," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

C. A. Gentry et al., "Application of Fully Ceramic Microencapsulated Fuel for Transuranic Waste Recycling in PWRs," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

K. S. Kim and M. L. Williams, "The Method of Characteristics for 2-D Multigroup and Pointwise Transport Calculations in SCALE/CENTRM," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange, Ill. (2012)

J. J. Jarrell et al., "Full Core Reactor Analysis: Running Denovo on Jaguar," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

N. Sly et al., "Verification of the Shift Monte Carlo Code," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

J. L. McDuffee and T. F. Daly, "Experimental and Computational Study of the Flux Spectrum in Materials Irradiation Facilities of the High Flux Isotope Reactor," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange, Ill. (2012)

B. T. Mervin et al., "Variance Estimation in Domain Decomposed Monte Carlo Eigenvalue Calculations," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

B. T. Rearden et al., "Enhancements in SCALE 6.1," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

H. J. Smith, "Modeling Depletion Simulations for a High-Burnup, Highly Heterogeneous BWR Fuel Assembly with SCALE," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

M. T. Pigni, M. E. Dunn, and K. H. Guber, "183W Resonance Parameter Evaluation in the Neutron Energy Range Up to 5keV," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

G. Arbanas et al., "Convergence of Legendre Expansion of Doppler-Broadened Double Differential Elastic Scattering Cross Section," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

C. M. Perfetti et al., "Development of Continuous-Energy Eigenvalue Sensitivity Coefficient Calculation Methods in the Shift Monte Carlo Code," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

C. M. Perfetti et al., "Determining Importance Weighting Functions for Contributon Theory Eigenvalue Sensitivity Coefficient Methodologies," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrangre Park, Ill. (2012)

J. L. Peterson and G. Ilas, "Calculation of Heating Values for the High Flux Isotope Reactor," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrangre Park, Ill. (2012)

T. Ivanova et al., "Benchmark on Sensitivity Calculation (Phase III)," PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)

G. F. Flanagan, "Response of the Fukushima Dai-ichi Nuclear Plant to the March 11, 2011, Earthquake in Japan," Proc. EERI 2012 Annual Meeting and National Earthquake Conference, Memphis, Tenn., April 10-13, 2012.

G. L. Bell et al., "Fuel Cycle Research and Development HFIR Irradiation Testing," presented at the Advanced Fuels Campaign Quarterly Meeting, April 4, 2012, Oak Ridge, Tenn.

B. Riemer et al., "Demonstration of Small Gas Bubbles for Mitigation of Cavitation Damage and Pressure Waves in Short-pulse Mercury Spallation Targets," Proc. 20th Meeting of the International Collaboration of Advanced Neutron Science (ICANS-XX), Bariloche, Argentina, March 4-9, 2012.

K. T. Clarno and R. L. Howard, Problem Specificiations for FY12 Modeling of UNF During Extended Storage, ORNL/TM-2012/80, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2012.

D. G. Renfro et al., Low-Enriched Uranium Fuel Conversion Activities for the High Flux Isotope Reactor, Annual Report for FY 2011, ORNL/TM-2011/507, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2012.

D. Ilas, Development of a Scale Model for High Flux Isotope Reactor Cycle 400, ORNL/TM-2011/367, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2012.

E. D. Blakeman, D. Ilas, and A. Y. Petrov, A Preliminary Analysis of Dose Rates Associated with ITER CVCS Equipment/Area Location, ORNL/TM-2012/46, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2012.

G. D. DelCul et al., "Macro TALSPEAK Separations of Am-CM from Fission Products - Implications for a Single Step Separation and Advanced Fuel Cycle Irradiation of Am-Cm," Ninth International Conference on Methods and Applications of Radioanalytical Chemistry (MARC IX), Kailua-Kona, Hi., March 25-30, 2012.

B. Philip, K. T. Clarno, R. S. Sampath, M. A. Berrill, and S. Allu, "A Jacobian Free Newton Krylov Method with Multilevel Block Preconditioning for Multi-Domain Quasistatic Thermomechanics," Twelfth Copper Mountain Conference on Iterative Methods, Copper Mountain, Colo., March 25-30, 2012.

S. P. Hamilton, K. T. Clarno, B. Philip, R. S. Sampath, M. A. Berrill, S. Allu, M. L. Baird, and J. E. Banfield, "Coupled Radiation Transport and Thermomechanics using the AMP and Denovo Codes," Twelfth Copper Mountain Conference on Iterative Methods, Copper Mountain, Colo., March 25-30, 2012.

B. Philip et al., "The Advanced Multi-Physics (AMP) Package," Twelfth Copper Mountain Conference on Iterative Methods, Copper Mountain, Colo., March 25-30, 2012.

E. D. Collins et al., "Macro TALSPEAK Separations of Am-Cm from Fisson Products - Implications for a Single Step Separation and Advanced Fuel Cycle Irradiation of Am-Cm," Methods and Application of Radioanalytical Chemistry (MARC IX), Kailua-Kona, Hawaii, March 25-30, 2012.

T. J. Harrison and A. L. Qualls, "Analysis of Burnup Effects on Reactor Control Strategies," Proc. of the Nuclear and Emerging Technologies for Space, The Woodlands, Tex., March 21-23, 2012.

R. A. Joseph III, A. L. Qualls, C. S. Chadwell, and E. F. Hancock, "The Fission Power System Control Drive Motor Testing," Proc. of the Nuclear and Emerging Technologies for Space, The Woodlands, Tex., March 21-23, 2012.

D. A. Reed, "Use of SCALE Sensitivity/Uncertainty Analysis Tools in the Design of Critical Experiments - Lessons Learned," presented at the NCSP Technical Seminar, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 14, 2012.

S. Goluoglu and C. M. Hopper, "Development and Deployment of 2-Week Nuclear Criticality Safety Training Course," presented at the NCSP Technical Seminar, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 14, 2012.

M. T. Pigni, L. C. Leal, M. E. Dunn, and V. Sobes, "Nuclear Data Evaluation Status for Tungsten Isotopes 182-184, 186W and 63,65Cu," presented at the NCSP Technical Seminar, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 14, 2012.

B. T. Rearden and W. J. Marshall, "Use of Sensitivity and Uncertainty Methods in the Analysis of Validation Outliers," presented at the NCSP Technical Seminar, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 14, 2012.

L. C. Leal and M. E. Dunn, "239Pu Resonance Region Evaluation," presented at the NCSP Technical Seminar, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 13, 2012.

T. M. Miller, "MAVRIC-S/U Development: Fixed Source Multi-group Sensitivity and Uncertainty Analysis," presented at the NCSP Technical Seminar, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 13, 2012.

T. M. Miller, "SILENE Benchmark Experiment for Criticality Accident Alarm Systems: Evaluation Progress in FY 2011," presented at the NCSP Technical Seminar, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 13, 2012.

K. H. Guber, "ORNL Neutron Cross-Section Measurements Activities," presented at the NCSP Technical Seminar, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 13, 2012.

B. T. Rearden, "Modernization of SCALE," presented at the NCSP Technical Seminar, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 13, 2012.

C. M. Hopper, "US DOE NCSP Criticality Safety Support Group (CSSG) Functions & Activities," presented at the NCSP Technical Seminar, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 13, 2012.

G. L. Yoder, Jr., et al., Vortex Diode Analysis and Testing for Fluoride Salt-Cooled High-Temperature Reactors, ORNL/TM-2011/425, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2012.

A. M. Bonavita, M. Monterial, and V. J. Jodoin, Updated Activities, Exposure Rates, and Gamma Spectra for Unfractionated Fission Products, ORNL/TM-2011/530, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2012.

E. Hardin et al., "Generic Repository Concepts and Thermal Analysis for Advanced Fuel Cycles," Proc. of the Waste Management Symposia Conference, Phoenix, Ariz., February 26-March 1, 2012.

E. D. Collins et al., "A Practical Approach to a Closed Nuclear Fuel Cycle and Sustained Nuclear Energy," Proc. of the WM2012 Symposia Annual Conference, Phoenix, Ariz., February 26-March 1, 2012.

D. A. Copinger, C. B. Oland, and D. J. Naus, A Summary of Aging Effects and Their Management in Reactor Spent Fuel Pools, Refueling Cavities, Tori, and Safety-Related Concrete Structures, ORNL/TM-2011/410, Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2012.

K. T. Clarno et al., Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations, ORNL/TM-2012/33, Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2012.