Reactor and Nuclear Systems Division

Reactor and Nuclear Systems Division
2011 Publications

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M. T. Pigni, "Measurement of the U-236(n,f) cross section from 170 meV to 2 MeV at the CERN n_TOF facility," Physical Review C 84(4) (2011).

M. T. Pigni, "Measurement of the neutron-induced fission cross-section of Am-243 relative to U-235 from 0.5 to 20 MeV," The European Physical Journal A (EPJ A) - Hadrons and Nuclei 47(12) (2011).

M. T. Pigni, "Au-197(n,gamma) cross section in the unresolved resonance region," Physical Review C 83(3) (2011).

M. T. Pigni, "Neutron-induced fission cross-section of U-233 in the energy range 0.5 < E-n < 20 MeV," The European Physical Journal A (EPJ A) - Hadrons and Nuclei 47(1) (2011).

K. C. Bledsoe, J. A. Favorite, and T. Aldemir, "Application of the Differential Evolution Method to Solving Inverse Transport Problems," Nuclear Science and Engineering 169(2), 208 (2011).

K. C. Bledsoe, J. A. Favorite, and T. Aldemir, "Using the Levenberg-Marquartdt Method for Solutions of Inverse Transport Problems in One-and Two-Dimensional Geometries," Nuclear Technology 176(1), 106 (2011).

M. A. Jessee, P. Turinsky, and H. S. Abdel-Khalik, "Many-Group Cross-Section Adjustment Techniques for Boiling Water Reactor Adaptive Simulation," Nuclear Science and Engineering 169(1), 40 (2011).

D. Chandler, T. Primm, J. D. Freels, and G. I. Maldonado, "Neutronics Modeling of the High Flux Isotope Reactor using COMSOL," Annals of Nuclear Energy 38, pp. 2594-2605 (2011).

P. E. Koehler et al., "New Techniques for Determining Spins and Parities of Neutron Resonances and Their Impact on Nuclear Astrophysics," Korean Physical Society 59, 2088 (2011).

D. A. Clayton and R. T. Wood, "The Role of Instrumentation and Control Technology in Enabling Deployment of Small Modular Reactors," Nuclear News 54(13), 42-47 (2011).

R. T. Jubin, et al., "Development of Advanced Cermet Waste Forms," Proc. 11th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, San Francisco, Calif., November 1-5, 2010 (2011).

L. C. Leal and K. Shibata, Assessment of the Unresolved Resonance Treatment for the Cross-Section and Covariance Representation, report by the Working Party on International Evaluation Co-operation of the NEA Nuclear Science Committee, Nuclear Energy Agency, Organisation for Economic Co-operation and Development (2011).

P. K. Jain, R. Uddin, and S. Singh, "Finite integral transform method to solve asymmetric heat conduction in a multilayer annulus with time-dependent boundary conditions," Nuclear Engineering and Design 83(2), 144-154 (2011).

G. Yesilyurt, K. T. Clarno, T. M. Evans, G. G. Davidson, and P. B. Fox, "C5 Benchmark Problem with Discrete Ordinate Radiation Transport Code DENOVO," Nuclear Technology 176(2), 274-283 (2011).

R. N. Christensen et al., "Design of a Scaled-down DRACS Test Facility for an AHTR," Trans. Am. Nucl. Soc. 105, 1031-1034 (2011).

R. J. Ellis, "Comparison of Calculated and Measured Neutron Fluence in Fuel/Cladding Irradiation Experiments in HFIR," Trans. Am. Nucl. Soc. 105, 808-810 (2011).

G. F. Flanagan, "ANS Standards Activities Related to Sodium-Cooled Small Modular Reactor," Trans. Am. Nucl. Soc. 105, 1133 (2011).

S. P. Hamilton and M. Benzi, "A Davidson Method for the k-Eigenvalue Problem," Trans. Am. Nucl. Soc. 105, 432-434 (2011).

S. P. Hamilton and K. T. Clarno, "Mathematical Framework for the Coupling of the AMP and Denovo Codes," Trans. Am. Nucl. Soc. 105, 515-517 (2011).

C. M. Hopper, "US DOE NCSP Training and Education Program Plan," Trans. Am. Nucl. Soc. 105, 599-600 (2011).

S. P. Monahan, T. P. McLaughlin, A. Garcia, C. Hopper, and G. E. Whitesides, "The Language of the Process Analysis Requirement and the Double Contingency Principle," Trans. Am. Nucl. Soc. 105, 551-552 (2011).

K. McCoy, R. Morris, B. Bevard, and P. Blanpain, "Hot Cell Examination of MOX Fuel from Nonproliferation Programs," Trans. Am. Nucl. Soc. 105, 385-386 (2011).

A. Ibrahim, D. E. Peplow, J. C. Wagner, S. W. Mosher, and T. M. Evans, " Acceleration of Monte Carlo Criticality Calculations Using Deterministic-Based Starting Sources," Trans. Am. Nucl. Soc. 105, 539-541 (2011).

J. J. Jarrell, R. E. Grove, and T. M. Evans, "A Cut-Cell Approach for 2D Cartesian Meshes that Preserves Orthogonal Grid Sweep Ordering," Trans. Am. Nucl. Soc. 105, 435-437 (2011).

B. L. Kirk, S. E. Skutnik, M. D. Eipeldauer, and J. M. Whitaker, "Nonproliferation-Focused Laboratory Internships as a Catalyst for University Safeguards Education," Trans. Am. Nucl. Soc. 105, 175-176 (2011).

D. Lee, M. L. Williams, B. J. Ade, and S. M. Bowman, "Verification of New Doubly-Heterogeneous Self-shielding Method in SCALE," Trans. Am. Nucl. Soc. 105, 849-850 (2011).

T. M. Miller and K. H. Reynolds, "SILENE Benchmark Critical Experiments for Criticality Accident Alarm Systems," Trans. Am. Nucl. Soc. 105, 609-610 (2011).

K. McCoy, R. N. Morris, B. B. Bevard, and P. Blanpain, "Hot Cell Examination of MOX Fuel from Nonproliferation Programs," Trans. Am. Nucl. Soc. 105, 385-386 (2011).

C. Morrow, B. R. Upadhyaya, and J. March-Leuba, "Thermal Camera Imaging for Security Monitoring of GCEP Systems," Trans. Am. Nucl. Soc. 105, 262-263 (2011).

M. D. Muhlheim, L. A. Hardin, D. Hardesty, and T. L. Wilson, "Things to Consider When Upgrading a Non-Power Reactor to a Digital I&C System," Trans. Am. Nucl. Soc. 105, 297-298 (2011).

E. A. Read, L. C. Leal, K. C. Bledsoe, B. L. Kirk, and C. R. E. De Oliveira, "Nuclear Data Error Propogation in Fusion Benchmark Calculations," Trans. Am. Nucl. Soc. 105, 464-465 (2011).

S. E. Skutnik, M. D. Eipeldauer, B. L. Kirk, and J. M. Whitaker, "ORNL Engagement with University Safeguards Education," Trans. Am. Nucl. Soc. 105, 171-172 (2011).

V. Sobes et al., "Thermal Total Cross Section Measurement for 63Cu and 65Cu at the MIT Reactor," Trans. Am. Nucl. Soc. 105, 557-558 (2011).

G. L. Yoder, Jr. et al., "Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs," Trans. Am. Nucl. Soc. 105, 1027-1030 (2011).

H. Akkurt, D. Wiarda, and K. F. Eckerman, "Recent Update to Radiation Organ Dose Estimation Tool PIMAL," Trans. Am. Nucl. Soc. 104, 635-636 (2011).

J. J. Carbajo, J. L. McDuffee, and A. L. Qualls, "Comparison of Thermal-Hydraulic Results from RELAP5-3D/ATHENA and ANSYS/CFX," Trans. Am. Nucl. Soc. 104, 1018-1019 (2011).

B. Mervin, S. Mosher, J. Wagner, and I. Maldonado, "Under-Prediction of Localized Tally Uncertainties in Monte Carlo Eigenvalue Calculations," Trans. Am. Nucl. Soc. 104, 329-330 (2011).

O. Lastres, D. Chandler, J. J. Jarrell, and G. I. Maldonado, "Studies of Plutonium-238 Production at the High Flux Isotope Reactor," Trans. Am. Nucl. Soc. 104, 716-718 (2011).

R. J. Ellis, G. D. DelCul, and E. D. Collins, "Physics Analyses of an Annular PWR Fuel Pellet Concept for Minor Actinide Utilization," Trans. Am. Nucl. Soc. 104, 665-667 (2011).

D. Wiarda, L. C. Leal, and M. E. Dunn, "Cross-Section Covariance Data Processing with the AMPX Module PUFF-IV," Trans. Am. Nucl. Soc. 104, 772-773 (2011).

P. K. Jain, J. D. Freels, and D. H. Cook, "COMSOL-based Multiphysics Simulations to Support HFIR's Conversion to LEU Fuel," Trans. Am. Nucl. Soc. 104, 1064-1066 (2011).

M. A. Jessee and M. D. DeHart, "TRITON: A Multi-Purpose Transport, Depletion, and Sensitivity and Uncertainty Analysis Module," ORNL/TM-2005/39, Oak Ridge National Laboratory, Oak Ridge, Tenn. (2011).

M. A. Jessee and M. D. DeHart, "NEWT: A New Transport Algorithm for Two-Dimensional Discrete Ordinates Analysis in Non-Orthogonal Geometries," ORNL/TM-2005/39, Oak Ridge National Laboratory, Oak Ridge, Tenn. (2011).

P. Pereslavtsev, A. Konobeyev, U. Fischer, and L. C. Leal, "Evaluation of (50)Cr, (52)Cr, (53)Cr, (54)Cr Neutron Cross Section Data for Energies up to 200 MeV," Journal of the Korean Physical Society 59(2), 931-934 (2011).

L. C. Leal, H. Derrien, K. H. Guber, G. Arbanas, and D. Wiarda, "Evaluation of the Chromium Resonance Parameters Including Resonance Parameter Covariance," Journal of the Korean Physical Society 59(2), 1644-1648 (2011).

C. Lampoudis, S. Kopecky, P. Schillebeeckx, P. Siegler, and K. H. Guber, "Neutron Total and Capture Cross Section of Tungsten Isotope," Journal of the Korean Physical Society 59(2), 1860-1863 (2011).

A. Trkov et al., "Covariances of Evaulated Nuclear Cross Section Data for (232)Th, (180,182,183,184,186)W and (55)Mn," Nuclear Data Sheets 112(12), 3098-3119 (2011).

A. Kahler et al., "ENDF/B-VII.1 Neutron Cross Section Data Testing with Critical Assembly Benchmarks and Reactor Experiments," Nuclear Data Sheets 112(12), 2997-3036 (2011).

M. B. Chadwick et al., "ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data," Nuclear Data Sheets 112(12), 2887-2996 (2011).

H. J. Smith, Characteristics of 17 x 17 Mixed UO2/TRISO Fuel Assemblies, ORNL/TM-2010/142, Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2011.

G. T. Mays et al., Application of Spatial Data Modeling and Geographical Information Systems (GIS) for Identification of Potential Siting Options for Various Electrical Generation Sources, ORNL/TM-2011/157, December 2011.

G. L. Bell et al., Deliverable Report - Summary of FY11 HFIR Irradiation Testing Activities, ORNL/TM-2011/476, Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2011.

B. L. Kirk, M. D. Eipeldauer, and M. J. Whitaker, Oak Ridge National Laboratory Next Generation Safeguards Initiative, ORNL/TM-2011/402, Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2011.

T. J. Harrison, K. W. Childs, and A. L. Qualls, Development of an Evolutionary Algorithm for HFIR Design Activities, ORNL/LTR-2011/382, Oak Ridge National Laboratory, Oak Ridge, Tenn., November 2011.

W. J. Marshall and B. T. Rearden, Criticality Safety Validation of Scale 6.1, ORNL/TM-2011/450, Oak Ridge National Laboratory, Oak Ridge, Tenn., November 2011.

A. S. Sabau et al., "Mixtures of CO2-SF6 as Working Fluids for Geothermal Plants," ASME 2011 International Mechanical Engineering Congress & Exposition, Denver Colo., November 11, 2011.

J. S. Neal et al., "Evaluation of Neutron and Gamma Detectors for High-Temperature Well-Logging Applications," Proc. 2nd Annual Future of Instrumentation International Workshop, Oak Ridge, Tenn., November 7-8, 2011.

J. A. March-Leuba and C. Thurston, "BWR Stability Methodology," CAMP Workshop, Philadelphia, Pa., November 7, 2011.

M. H. Piro, T. M. Besmann, and K. T. Clarno, M3 Milestone - Equilibrium Thermodynamics in the Advanced Multi-Physics Code, ORNL/TM-2011/434, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2011.

J. C. Wagner, S. W. Mosher, T. M. Evans, D. E. Peplow, and J. A. Turner, "Hybrid and Parallel Domain-Decomposition Methods Development to Enable Monte Carlo for Reactor Analyses," Progress in Nuclear Science and Technology 2, 815-820, October 2011.

J. C. Wagner, D. E. Peplow, S. W. Mosher, and T. M. Evans, "Review of Hybrid (Deterministic/Monte Carlo) Radiation Transport Methods, Codes, and Applications at Oak Ridge National Laboratory," Progress in Nuclear Science and Technology 2, 808-814, October 2011.

T. D. Jackson, D. F. Hollenbach, and D. Shedlock, "Investigation of Backscatter X-ray Imaging Techniques for Uranium Dioxide Fuel Rods," Research in Nondestructive Evaluation 22, 4 (2011).

M. W. Francis and V. J. Jodoin, Compendium of Tools and Techniques Used to Collect Local Fallout Debris Samples, ORNL/TM-2010/208, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2011.

D. L. Moses and W. R. Corwin, Very High-Temperature Reactor (VHTR) Proliferation Resistance and Physical Protection (PR&PP), ORNL/TM-2010/163, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2011.

B. J. Ade and I. C. Gauld, Decay Heat Calculations for PWR and BWR Assemblies Fueled with Uranium and Plutonium Mixed Oxide Fuel using SCALE, ORNL/TM-2011/290, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2011.

K. C. Bledsoe, J. A. Favorite, and T. Aldemir, "Application of the Differential Evolution Method to Solving Inverse Transport Problems," Nuclear Science and Engineering 169(2), 208-221 (October 2011).

G. F. Flanagan, "ANS Working Group 54.1 - Nuclear Safety Criteria and Design Process for Sodium-Cooled Reactor Nuclear Power Plants," Proc. 2011 American Nuclear Society Winter Meeting and Nuclear Technology Expo, Washington, D.C., October 30-November 3, 2011.

B. B. Bevard, K. McCoy, R. N. Morris, and P. Blanpain, "Hot Cell Examination of MOX Fuel from Nonproliferation Program," Proc. 2011 American Nuclear Society Winter Meeting and Nuclear Technology Expo, Washington, D.C., October 30-November 3, 2011.

A. L. Qualls, "Graphite Fuel Development for Nuclear Thermal Propulsion," Proc. 2011 American Nuclear Society Winter Meeting and Nuclear Technology Expo, Washington, D.C., October 30-November 3, 2011.

G. Arbanas, A. K. Kerman, H. Nam, and J. R. Stone, "Neutron Matter as a Composite Bose-Fermi Superfluid," 2011 Fall Meeting of the APS Division of Nuclear Physics, East Lansing, Mich., October 26-29, 2011.

B. R. Grogan and J. T. Mihalczo, "Identification of Light Isotopes Using Time-Tagged Neutron Scattering," INMM Central Regional Chapter Fall Meeting, Oak Ridge, Tenn., October 24-25, 2011.

B. L. Kirk, M. J. Whitaker, and M. D. Eipeldauer, "Next Generation Safeguards Initiative (NGSI) - University Curriculum Development," INMM Central Regional Chapter Fall Meeting, Oak Ridge, Tenn., October 24-25, 2011.

M. J. Harrison, Q. Cherel, and M. Monterial, "Design of a Moderated Multi-Detector Neutron Spectrometer for Optimal Specificity," IEEE Nuclear Science Symposium, Valencia, Spain, October 23-29, 2011.

D. G. Renfro et al., "Continuing LEU Conversion Activities at the High Flux Isotope Reactor," 33rd International Meeting on Reduced Enrichment for Research and Test Reactors, Santiago, Chile, October 23-27, 2011.

D. G. Renfro et al., "LEU Conversion Activities at the High Flux Isotope Reactor," 33rd International Meeting on Reduced Enrichment for Research and Test Reactors, Santiago, Chile, October 23-27, 2011.

J. D. Freels and P. K. Jain, "Multiphysics Simulations in the Complex 3D Geometry of the High Flux Isotope Reactor Fuel Elements Using COMSOL," COMSOL Conference, Newton, Mass., October 13-15, 2011.

D. Chandler, J. D. Freels, G. I. Maldonado, and T. Primm, "COMSOL-based Nuclear Reactor Kinetics Studies at the HFIR,"COMSOL Conference, Newton, Mass., October 13-15, 2011.

D. E. Holcomb and J. Uhlir, "Collaborative Project on Fluoride Salt Cooled High Temperature Reactor Technology Development," Transatlantic Nuclear Days - International Conference on Global Cooperation for Future Development of Nuclear Power, Prague, Czech Republic, October 6-7, 2011.

M. A. Jessee, P. Turinsky, and H. Abdel-Khalik, "Many-Group Cross-Section Adjustment Techniques for Boiling Water Reactor Adaptive Simulation," Nuclear Science and Engineering 169(1), 40-55 (September 2011).

D. E. Holcomb, F. J. Peretz, and A. L. Qualls, Advanced High Temperature Reactor Systems and Economic Analysis, ORNL/TM-2011/364, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2011.

A. L. Qualls, M. S. Cetiner, and T. L. Wilson, Advanced High Temperature Reactor Dynamic System Model Development, ORNL/TM-2012/174, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2011.

D. E. Holcomb et al., Core and Refueling Design Studies for the Advanced High Temperature Reactor, ORNL/TM-2011/365, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2011.

R. T. Wood and B. R. Upadhyaya, "An Approach to Autonomous Control for Space Nuclear Power Systems," in Nuclear Power - Control, Reliability and Human Factors, 101-118 (2011).

K. A. Terrani, L. L. Snead, and J. C. Gehin, "FCM Fuel Development for SMR Applications," ASME SMR-2011, Washington, D.C., September 28, 2011.

M. H. Piro, T. M. Besmann, S. Simunovic, and K. T. Clarno, "Progress in Thermodynamic Equilibrium Computations in the Advanced Multi-Physics Code," Materials Modeling and Simulation of Nuclear Fuels (MMSNF), Aix en Provence, France, September 26, 2011.

J. McFarlane, A. L. Qualls, A. S. Sabau, S. A. Wright, and H. Yin, "Air versus Water Cooling in Engineered Geothermal Systems," Groundwater Protection Council Annual Forum, Atlanta, Ga., September 24-28, 2011.

J. McFarlane et al., "Ways to Minimize Water Usage in Engineered Geothermal Systems," Groundwater Protection Council Annual Forum, Atlanta, Ga., September 24-28, 2011.

G. Arbanas, C. A. Bertulani, D. J. Dean, A. K. Kerman, and K. J. Roche, "Extending the Kawai-Kerman-McVoy Statistical Theory of Nuclear Reactions to Doorway States," CNR 2011, Prague, Czech Republic, September 19-23, 2011.

G. Arbanas, C. A. Bertulani, D. J. Dean, A. K. Kerman, and K. J. Roche, "Extending the Kawai-Kerman-McVoy Statistical Theory of Nuclear Reactions to Intermediate Structure via Doorways," CNR 2011, Prague, Czech Republic, September 19-23, 2011.

R. D. Busch and K. C. Bledsoe, "The Effect of U-234 Content on the Neutronic Behavior of Uranium Systems," Proc. International Conference on Nuclear Criticality (ICNC) 2011, Edinburgh, Scotland, September 19-22, 2011.

M. E. Dunn et al., "Resonance Region Cross-Section Data Advancements for Nuclear Criticality Safety Applications and ENDF/B-VII.1," Proc. International Conference on Nuclear Criticality (ICNC) 2011, Edinburgh, Scotland, September 19-22, 2011.

K. H. Guber et al., "New Improved Nuclear Data for Nuclear Criticality and Safety," Proc. International Conference on Nuclear Criticality (ICNC) 2011, Edinburgh, Scotland, September 19-22, 2011.

L. C. Leal et al., "Resonance Evaluation of 48Ti Including Covariance for Criticality Safety Applications," Proc. International Conference on Nuclear Criticality (ICNC) 2011, Edinburgh, Scotland, September 19-22, 2011.

L. C. Leal, K. H. Guber, G. Arbanas, D. Wiarda, and P. E. Koehler, "Resonance Evaluation of 48Ti Including Covariance for Criticality Safety Application," Proc. International Conference on Nuclear Criticality (ICNC) 2011, Edinburgh, Scotland, September 19-22, 2011.

G. Radulescu, I. C. Gauld, G. Ilas, and J. C. Wagner, "An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Isotopic Composition Predictions," Proc. International Conference on Nuclear Criticality (ICNC) 2011, Edinburgh, Scotland, September 19-22, 2011.

B. T. Rearden, D. A. Reed, R. A. Lefebvre, D. Mueller, and W. J. Marshall, "Scale/TSUNAMI Sensitivity Data for ICSBEP Evaluations," Proc. International Conference on Nuclear Criticality (ICNC) 2011, Edinburgh, Scotland, September 19-22, 2011.

B. T. Rearden et al., "Scale 6.1 Enhancements for Nuclear Criticality Safety," Proc. International Conference on Nuclear Criticality (ICNC) 2011, Edinburgh, Scotland, September 19-22, 2011.

C. M. Hopper, "Status and Value of International Standards for Nuclear Criticality Safety," Proc. International Conference on Nuclear Criticality (ICNC) 2011, Edinburgh, Scotland, September 19-22, 2011.

C. M. Hopper, "The Development, Content, Design, and Conduct of the 2011 Piloted US DOE Nuclear Criticality Safety Program Criticality Safety Engineering Training and Education Project," Proc. International Conference on Nuclear Criticality (ICNC) 2011, Edinburgh, Scotland, September 19-22, 2011.

T. M. Miller et al., "2010 Criticality Accident Alarm System Benchmark Experiments at the CEA Valduc Silene Facility," Proc. International Conference on Nuclear Criticality (ICNC) 2011, Edinburgh, Scotland, September 19-22, 2011.

J. M. Scaglione, D. Mueller, and J. C. Wagner, "An Approach for Validating Actinide and Fission Product Burnup Criticality Safety Analyses-Criticality (keff) Predictions," Proc. International Conference on Nuclear Criticality (ICNC) 2011, Edinburgh, Scotland, September 19-22, 2011.

D. Mueller et al., "An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses - Criticality (Keff) Predictions," Proc. International Conference on Nuclear Criticality (ICNC) 2011, Edinburgh, Scotland, September 19-22, 2011.

G. Arbanas et al., "Covariance Matrix of a Double-Differential Elastic Scattering Cross Section," 2nd Workshop on Neutron Cross Section Covariances, Vienna, Austria, September 14-16, 2011.

K. McCoy, R. N. Morris, B. B. Bevard, and P. Blanpain, "Performance of MOX Fuel from NonProliferation Programs," 2011 Water Reactor Fuel Performance Meeting, Chengdu, China, September 11-14, 2011.

K. McCoy, R. N. Morris, B. B. Bevard, and P. Blanpain, "Examination of Weapons-Grade MOX Fuel," 2011 Water Reactor Fuel Performance Meeting, Chengdu, China, September 11-14, 2011.

M. E. Dunn, H. Derrien, L. C. Leal, C.-S. Gil, and D. Kim, "Resonance Region Nuclear Data Analysis to Support Advanced Fuel Cycle Development," Proc. International Conference on Nuclear Data for Science and Technology 2010, Jeju Island, South Korea, April 26-30, 2010 (August 2011).

L. H. Petrie, Jr., R. A. Lefebvre, and D. Wiarda, Standard Composition Library, ORNL/TM-2005/39 (Sect. M8), Oak Ridge National Laboratory, Oak Ridge, Tenn., August 2011.

A. M. Ibrahim et al., "Global Evaluation of Prompt Dose Rates in ITER Using Hybrid Monte Carlo/Deterministic Techniques," Fusion Science and Technology 60, 676-680 (August 2011).

G. T. Mays, "Applying Geographic Information System-Based Tool for Evaluating Siting Challenges for New Nuclear Capacity - Water and Electric Transmission Availability," 2011 Utility Working Conference and Vendor Technology Expo, Washington, D.C., August 17, 2011.

V. J. Jodoin, R. W. Lee, D. E. Peplow, and J. P. Lefebvre, "Application of the DELFIC Fallout Planning Tool and the ORIGEN Fallout Analysis Tool to National Technical Nuclear Forensics (NTNF)," IEEE 3rd International Joint Topical Meeting on Emergency Preparedness & Response and Robotics & Remote Systems, Knoxville, Tenn., August 7-10, 2011.

V. J. Jodoin, R. W. Lee, D. E. Peplow, and J. P. Lefebvre, "Application of the ORIGEN Fallout Analysis Tool and the DELFIC Fallout Planning Tool to National Technical Nuclear Forensics," ANS EPRRSD - 13th Robotics & Remote Systems for Hazardous Environments - 11th Emergency Preparedness & Response, Knoxville, Tenn., August 7-10, 2011.

A. M. Ibrahim et al., "ITER Neutronics Modeling Using Hybrid Monte Carlo/Deterministic and CAD-Based Monte Carlo Methods," Nuclear Technology 175, 1-8 (July 2011).

E. C. Fortune, I. C. Gauld, and C. Wang, "Gamma Dose Rate Near a New (252)Cf Brachytherapy Source," Nuclear Technology 175 (1), 73-76 (July 2011).

J. C. Gehin et al., Fast Spectrum Molten Salt Reactor Options, ORNL/TM-2011/105, Oak Ridge National Laboratory, Oak Ridge, Tenn., July 2011.

S. Sherbini, D. Ilas, K. Eckerman, and J. DeCicco, "Correction Factors Applied to Finger Dosimetry: A Theoretical Assessment of Appropriate Values for Use in Handling Radiopharmaceuticals," Health Physics 101 (1), 1-12 (July 2011).

R. A. Joseph, III, C. O. Slater, T. M. Evans, S. W. Mosher, and J. O. Johnson, "Sensitivities and Uncertainties Related to Numerics and Building Features in Urban Modeling," Nuclear Technology 175 (1), 286-300 (July 2011).

B. T. Rearden, "Scale Newsletter, Number 43, Summer 2011," Oak Ridge National Laboratory, Oak Ridge, Tenn., July 2011.

A. L. Qualls and E. F. Hancock, "Recapturing NERVA-Derived Fuels for Nuclear Thermal Propulsion," 47th AIAA/ASME/SAE/ASEE Joint Propulsion Conference & Exhibit, San Diego, Calif., July 31-August 3, 2011.

A. L. Qualls, G. F. Flanagan, and G. L. Bell, "Recapturing NERVA-Derived Fuels for Nuclear Thermal Propulsion," 47th AIAA/ASME/SAE/ASEE Joint Propulsion Conference & Exhibit, San Diego, Calif., July 31-August 3, 2011.

Z. W. Bell et al., "Python for Development of OpenMP and CUDA Kernels for Multidimensional Data," Proc. 2011 Symposium on Application Accelerators in High Performance Computing (SAAHPC'11), Knoxville, TN, July 19-21, 2011, Conference Publishing Services (CPS), IEEE Computer Society, Los Alamitos, CA (2011).

B. L. Broadhead," Nuclear Archaeology for CANDU Power Reactors," Proc. INMM 52nd Annual Meeting, Palm Desert, Calif., July 17-21, 2011.

J. T. Mihalczo, T. E. Valentine, E. D. Blakeman, and V. Pare, "Cf Neutron Time of Flight Transmission for Material Identification," Proc. INMM 52nd Annual Meeting, Palm Desert, Calif., July 17-21, 2011.

J. T. Mihalczo, T. E. Valentine, E. D. Blakeman, and V. Pare, "Cf Neutron Time of Flight Transmission for Material Identification for Weapons Trainers," Proc. INMM 52nd Annual Meeting, Palm Desert, Calif., July 17-21, 2011.

J. A. Mullens et al., "Neutron Radiography and Fission Mapping Measurements of Nuclear Materials with Varying Composition and Shielding," Proc. INMM 52nd Annual Meeting, Palm Desert, Calif., July 17-21, 2011.

C. F. Weber, V. A. Protopopescu, A. A. Solodov, and C. E. Romano, "Inverse Solutions in Spectroscopic Analysis with Applications to Problems in Global Safeguards," Proc. INMM 52nd Annual Meeting, Palm Desert, Calif., July 17-21, 2011.

M. W. Francis and J. R. Cheatham, "Determining Spent Nuclear Fuel's Plutonium Content, Initial Enrichment, Burnup, and Cooling Time with Isotopic Information," Proc. INMM 52nd Annual Meeting, Palm Desert, Calif., July 17-21, 2011.

J. T. Mihalczo, T. E. Valentine, E. D. Blakeman, and V. Pare, "CF Neutron Time of Flight Transmission for Material Identification," Proc. INMM 52nd Annual Meeting, Palm Desert, Calif., July 17-21, 2011.

J. T. Mihalczo, T. E. Valentine, E. D. Blakeman, and V. Pare, "CF Neutron Time of Flight Transmission for Material Identification for Weapons Trainers," Proc. INMM 52nd Annual Meeting, Palm Desert, Calif., July 17-21, 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.

G. Muralidharan, D. F. Wilson, L. R. Walker, M. L. Santella, and D. E. Holcomb, Cladding Alloys for Fluoride Salt Compatibility, ORNL/TM-2011/95, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 2011.

J. D. Freels et al., Preliminary Multiphysics Analyses of HFIR LEU Fuel Conversion using COMSOL, ORNL/TM-2011/7, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 2011.

D. Chandler, T. Primm, R. W. Hobbs, and G. I. Maldonado, "Black Rabbit Ejection Studies and COMSOL Kinetics Modeling Development at HFIR," Proc. 2011 American Nuclear Society Annual Meeting, Hollywood, Fla., June 26-30, 2011.

G. Del Cul et al., "Determination of Characteristics of Cermet High-Level Waste Forms," Proc. 2011 American Nuclear Society Annual Meeting, Hollywood, Fla., June 26-30, 2011.

S. Vladimir et al., "Processing and Testing New 240PU Resolved Resonance Evaluation," Proc. 2011 American Nuclear Society Annual Meeting, Hollywood, Fla., June 26-30, 2011.

J. C. Wagner et al., "Hybrid and Parallel Domain-Decomposition Methods Development to Enable Monte Carlo for Reactor Analyses," Proc. 2011 American Nuclear Society Annual Meeting, Hollywood, Fla., June 26-30, 2011.

T. Primm and G. Ilas, "Justification for an Increase in Authorized Operating Power at HFIR," Proc. 2011 American Nuclear Society Annual Meeting, Hollywood, Fla., June 26-30, 2011.

B. T. Rearden and D. Mueller, "Uncertainty Quantification Techniques of SCALE/TSUNAMI," Proc. 2011 American Nuclear Society Annual Meeting, Hollywood, Fla., June 26-30, 2011.

M. L. Williams and B. T. Rearden, "Self-Shielding Effects for Uncertainty Analysis," Proc. 2011 American Nuclear Society Annual Meeting, Hollywood, Fla., June 26-30, 2011.

V. J. Jodoin, R. W. Lee, D. E. Peplow, and J. P. Lefebvre, "Application of the Oak Ridge Isotope Generation Code and the Defense Land Fallout Interpretive Code to National Technical Nuclear Forensics," Health Physics Society 56th Annual Meeting, Palm Beach, Fla., June 26-30, 2011.

M. T. Pigni, "23Na Cross-section Evaluation," Summer Nuclear Data Week, Montauk, N.Y., June 20-24, 2011.

J.-A. J. Wang, H. Wang, Y. Yan, R. L. Howard, and B. B. Bevard, Spent Nuclear Fuel Vibration Integrity Study Progress Report, ORNL/TM-2010/288, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2011.

S. Goluoglu et al., "Monte Carlo Criticality Methods and Analysis Capabilities in SCALE," Nucl. Technol. 174(2), 214-235, May 2011.

D. E. Peplow, "Monte Carlo Shielding Analysis Capabilities with MAVRIC," Nucl. Technol. 174(2), 289-313, May 2011.

S. M. Bowman, "SCALE 6: Comprehension Nuclear Safety Analysis Code System," Nucl. Technol. 174(2), 126-148 (May 2011).

M. D. DeHart and S. M. Bowman, "Reactor Physics Methods and Analysis Capabilities in SCALE," Nucl. Technol. 174(2), 196-213 (May 2011).

M. L. Williams, "Resonance Self-Shielding Methodologies in SCALE 6," Nucl. Technol. 174(2), 149-168 (May 2011).

E. D. Blakeman, Modeling and Analysis of the ORNL HTGR Neutron-Streaming Experiment using SCALE/MAVRIC, ORNL/TM-2010/345, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2011.

I. C. Gauld et al., "Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE," Nucl. Technol. 174(2), 169-195, May 2011.

B. T. Rearden, M. L. Williams, M. A. Jessee, D. Mueller, and D. Wiarda, "Sensitivity and Uncertainty Analysis Capabilities and Data in SCALE," Nucl. Technol. 174(2), 236-288, May 2011.

I. C. Gauld, ORIGEN-S: Depletion Module to Calculate Neutron Activation, Actinide Transmutation, Fission Product Generation and Radiation Source Terms, Sect. F7 of ORNL/TM-2005/39, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2011.

I. C. Gauld, COUPLE: A Nuclear Decay and Cross-Section Data Processing Code for Creating ORIGEN-S Libraries, Sect. F6 of ORNL/TM-2005/39, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2011.

G. Ilas and T. Primm, Low-Enriched Uranium Fuel Design with Two-Dimensional Grading for the High Flux Isotope Reactor, ORNL/TM-2010/318, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2011.

J. C. Wagner, Foreword (Special SCALE Issue), Nucl. Technol. (May 2011).

M. Willingham et al., Environmental Impact Statement for Combined Licenses (COLs) for Comanche Peak Nuclear Power Plant Units 3 and 4; Final Report (Volume 1, Chapters 1-10), NUREG-1943, Vol. 1, prepared for the U. S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2011.

M. Willingham et al., Environmental Impact Statement for Combined Licenses (COLs) for Comanche Peak Nuclear Power Plant Units 3 and 4; Final Report (Volume 2, Appendices A-J), NUREG-1943, Volume 2, prepared for the U. S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2011.

A. S. Sabau, H. Yin, A. L. Qualls, and J. McFarlane, "Investigations of supercritical CO2 Rankine cycles for geothermal power plants," Proc. Supercritical CO2 Power Cycle Symposium, Boulder, Colo., May 25, 2011.

E. D. Collins et al., "Comparative Studies of U/TRU Co-Conversion Processes," presented at the 35th Actinide Separations Conference, Charlotte, N.C., May 24, 2011.

E. D. Collins et al., "Comparative Studies of U/TRU Co-Conversion Processes," 35th Annual Actinide Separations Conference, Charlotte, N.C., May 24, 2011.

B. L. Kirk, "Shielding Integral Benchmark Archive and Database (SINBAD)," Proc. of the 14th International Symposium on Reactor Dosimetry, Bretton Woods, N.H., May 22-27, 2011.

J. M. Risner et al., "Development and Testing of the VITAMIN-B7/BUGLE-B7 Coupled Neutron-Gamma Multigroup Cross-Section Libraries," Proc. of the 14th International Symposium on Reactor Dosimetry, Bretton Woods, N.H., May 22-27, 2011.

B. L. Kirk, R. E. Grove, I. Kodeli, E. Sartori, and J. Gulliford, "Shielding Integral Benchmark Archive and Database (SINBAD)," Proc. of the 14th International Symposium on Reactor Dosimetry, Bretton Woods, N.H., May 22-27, 2011.

I. Remec, R. M. Ronningen, and L. Heilbronn, "Benchmarking of Heavy Ion Transport Codes," Proc. of the 14th International Symposium on Reactor Dosimetry, Bretton Woods, N.H., May 22-27, 2011.

J. A. March-Leuba and T. Uckan, "An Advanced Flow Monitor for Detecting Potential Diversion of Enriched Uranium at Gaseous Centrifuge Enrichment Plants," presented at the Global Safeguards Program Review Meeting, Albuquerque, N. Mex., May 10, 2011.

G. Arbanas, M. E. Dunn, and D. Wiarda, "Computation of Large Covariance Matrices by SAMMY on Graphical Processing Units and Multicore CPUs," International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), Rio de Janeiro, Brazil, May 8-12, 2011.

G. Arbanas et al., "Computation of Temperature-Dependent Legendre Moments of a Double-Differential Elastic Cross Section," International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), Rio de Janeiro, Brazil, May 8-12, 2011.

B. Mervin, G. I. Maldonado, S. W. Mosher, and J. C. Wagner, "Uncertainty Analyses for Localized Tallies in Monte Carlo Eigenvalue Calculations," Proc. of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), Rio de Janeiro, Brazil, May 8-12, 2011.

G. Yesilyurt, K. T. Clarno, I. C. Gauld, and J. Galloway, "Modular ORIGEN-S for Multi-Physics Code Systems," Proc. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), Rio de Janeiro, Brazil, May 8-12, 2011.

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.

K. C. Bledsoe, J. A. Favorite, and T. Aldemir, "A comparison of the Covariance Matrix Adaptation Evolution Strategy and the Levenberg-Marquardt method for solving multidimensional inverse transport problems," Annals of Nuclear Energy 38(4), 897-904, April 2011. 

C. V. Parks, J. C. Wagner, D. Mueller, and I. C. Gauld, "Development of Technical Basis for a Burnup Credit Regulatory Guidance in the United States," Proc. PATRAM 2010, London, U.K., October 3-8, 2010 (April 2011).

J. M. Scaglione and J. C. Wagner, "Review of Yucca Mountain Disposal Criticality Studies," Proc. of the International High-Level Radioactive Waste Management Conference, Albuquerque, N.M., April 2011.

U. Mertyurek, M. W. Francis, and I. C. Gauld, SCALE 5 Analysis of BWR Spent Nuclear Fuel Isotopic Compositions Safety Studies, ORNL/TM-2010/286, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2011.

R. T. Wood and M. E. Waterman, "Strategies for Diversity Usage to Mitigate Postulated Common Cause Failure Vulnerabilities," Journal of the UK Safety and Reliability Society, 30(4), 56-77, April 2011.

L. A. Boatner, J. S. Neal, Z. W. Bell, J. A. Kolopus, and H. Akkurt, "The Characterization of Scintillator Performance at Elevated Temperatures up to 400 Degrees Centigrade," 2011 MRS Spring Meeting, San Francisco, CA., April 25-29, 2011.

A. M. Ibrahim, et al., "Global Evaluation of Prompt Dose Rates in ITER Using FW-CADIS," Proc. American Nuclear Society Student Conference, Atlanta, Ga., April 14-17, 2011.

O. A. Omitaomu, R. Belles, S. W. Hadley, G. T. Mays, and B. R. Blevins, "Spatial Modeling and Site Suitability Assessment for Compressed Air Energy Storage," Proc. of Association of American Geographers, Seattle, Wash., April 12-16, 2011.

R. T. Jubin et al., "Cermet High-Level Waste Forms," 13th International High-Level Radioactive Waste Management Conference (IHLRWMC-2011), Albuquerque, N.M., April 10-14, 2011.

G. T. Mays, R. Belles, and O. A. Omitaomu, "A Geographic Information System-Based Tool for Evaluating Siting Options," Proc. of the International High-Level Radioactive Waste Management Conference, Albuquerque, N.M., April 10-14, 2011.

G. Radulescu and J. C. Wagner, "Review of Results for the OECD/NEA Phase VII Benchmark:  Study of Spent Fuel Compositions for Long-Term Disposal," Proc. of the International High-Level Radioactive Waste Management Conference, Albuquerque, N.M., April 10-14, 2011.

E. D. Collins, B. B. Spencer, and G. D. DelCul, "Importance of Decay Time on HLW Disposal," Proc. of the International High-Level Radioactive Waste Management Conference, Albuquerque, N.M., April 10-14, 2011.

J. M. Scaglione and J. C. Wagner, "Review of Yucca Mountain Disposal Criticality Studies," Proc. of the International High-Level Radioactive Waste Management Conference, Albuquerque, N.M., April 10-14, 2011.

T. M. Evans, "CASL:  Consortium for Advanced Simulation of Light Water Reactors, Neutronics and 3D Sn Transport," HPC Users Forum, Houston, Tex., April 6, 2011.

I. Remec and K. B. Bekar, "Shielding Design For The SNS Dual Beamline Serving USANS and NOMAD Instruments," Proc. of the Tenth International Topical Meeting on Nuclear Applications of Accelerators (AccApp11), Knoxville, Tenn., April 3-7, 2011.

L. J. Ott and J. L. McDuffee, "The ORNL High Flux Isotope Reactor and New Advanced Fuel Testing Capabilities," Proc. of the 15th International Topical Meeting on Research Reactor Fuel Management (RRFM), March 20-24, 2011, Rome, Italy.

M. E. Dunn, L. C. Leal, K. H. Guber, D. Wiarda, and G. Arbanas, "ORNL Nuclear Data Accomplishments for FY 2010," presented at the NCSP U. S. DOE Technical Seminar, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2, 2011.

E. D. Collins, G. D. DelCul, D. S. Terekov, and N. V. Emmanuel, "Recycle of Zirconium from Used Nuclear Fuel Cladding - A Major Element of Waste Reduction," Waste Management Symposia, Phoenix, Ariz., February 27-March 3, 2011.

J. Bess, K. C. Bledsoe, and B. T. Rearden, "Evaluation of HEU-Beryllium Benchmark Experiments to Improve Computational Analysis of Space Reactors," Nuclear and Emerging Technologies for Space 2011 (NETS-2011), Albuquerque, N. Mex., February 7-10, 2011.

V. J. Jodoin, Characterization of Fallout from an Urban Nuclear Detonation: Modification of DELFIC for Urban Scenarios, ORNL/TM-2011/50, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2011.

J. J. Carbajo, Modifications to the VV PHTS RELAP5 Model, ORNL/TM-2011/1 (US ITER 12103-TD0004-R00), Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2011.

A. L. Qualls and D. J. Walter, "Fission Surface Power System Power Control Strategies," Nuclear and Emerging Technologies for Space 2011 (NETS 2011), Albuquerque, N. Mex., February 7-10, 2011

D. H. Cook et al., Design Study for a Low-Enriched Uranium Code for the High Flux Isotope Reactor, Annual Report for FY 2010, ORNL/TM-2011/6, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2011.

S. R. Greene 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, Oak Ridge, Tenn., February 2011.

K.-S. Kim and M. D. DeHart, "Unstructured partial- and net-current based coarse mesh finite difference acceleration applied to the extended step characteristics method in NEWT," Annals of Nuclear Energy 38(2-3), 527-534, February 2011.

G. Muralidharan, D. F. Wilson, M. L. Santella, and D. E. Holcomb, Cladding Alloys for Fluoride Salt Compatibility, ORNL/TM-2010/319, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2011.

V. C. Paquit, M. W. Wendel, D. K. Felde, and B. Riemer, "Quantitative measurement by artificial vision of small bubbles in flowing mercury," Proc. of the SPIE Electronic Imaging – Image Processing:  Machine Vision Applications IV Conference, San Francisco, Calif., February 2011.

R. M. Westfall and C. M. Hopper, DOE/EM Criticality Safety Needs Assessment, ORNL/TM-2010/97, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2011.

G. L. Yoder Jr., K. Harvey, and J. J. Ferrada,Thermal Analysis of the Divertor Primary Heat Transfer System Piping During the Gas Baking Process, ORNL/TM-2010/115 (US ITER 12102-TD0001-R00), prepared for the US ITER Project Office by Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2011.

R. T. Jubin et al., "Development of Advanced Cermet Waste Forms," Proc. Waste Management 2011, Phoenix, Ariz., February 27-March 3, 2011.

R. T. Jubin et al., "Development of a CERMET High-Level Waste Form," Proc. Waste Management 2011, Phoenix, Ariz., February 27-March 3, 2011.

T. E. Valentine, "Nuclear Energy Policy Issues," Women in Nuclear Region II Conference, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 7, 2011.

B. L. Kirk, "ORNL University Outreach," Women in Nuclear Region II Conference, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 6-9, 2011.

I. C. Gauld, G. Ilas, and G. Radulescu, Uncertainties in Predicted Isotopic Compositions for High Burnup PWR Spent Nuclear Fuel, ORNL/TM-2010/41 (NUREG/CR-7012), prepared for the Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2011.

G. Ilas and I. C. Gauld, Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation – Vandelios II Reactor, ORNL/TM-2009/321, prepared for the Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2011.

D. Wiarda et al., Production and Testing of the VITAMIN-B7 Fine-Group and BUGLE-B7 Broad-Group Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data, ORNL/TM-2011/12, Oak Ridge National Laboratory, January 2011.