Reactor and Nuclear Systems Division

Reactor and Nuclear Systems Division
2013 Publications

L. J. Ott, et al., "Preparation of Prototypic Irradiated Hydrided-Zircaloy Cladding for UFDC Programs," Proc. LWR Fuel Performance Meeting/Top Fuel 2013, Charlotte, North Carolina., September 15-19, 2013.

D. Wang et al., "Implementation and Assessment of High-Resolution Numerical Methods in TRACE," Nuclear Engineering and Design, 263, 327-341 (2013).

L. A. Boatner et al., "The Characterization of Scintillator Performance at Temperatures up to 400 Degrees Centigrade," Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 709, 95-107 (2013).

S. L. Hogle, G. I. Maldonado, and C. W. Alexander, "Increasing transcurium production efficiency through direct resonance shielding," Annals of Nuclear Energy 60, 267-273 (2013).

B. T. Mervin, G. I. Maldonado, S. W. Mosher, and J. C. Wagner, "Uncertainty Under-Prediction in Monte Carlo Eigenvalue Calculations," Nuclear Science and Engineering 173, 276-292 (2013).

H. Yin et al., "Mixtures of SF6 - CO2 as working fluids for geothermal power plants," Applied Energy 106(6), 243 (2013).

M. H. Piro et al., "Coupled thermochemical, isotopic evolution and heat transfer simulations in highly irradiated UO2 nuclear fuel," Journal of Nuclear Materials 441, 240 (2013).

H. Wang et al., "Development of U-Frame Bending System for Studying the Vibration Integrity of Spent Nuclear Fuel," Journal of Nuclear Materials 440, 201-213 (2013).

M. L. Williams et al., "A Statistical Sampling Method for Uncertainty Analysis with SCALE and UXUSA," Nuclear Technology 183(3), 515-526 (2013).

C. McGraw and G. Ilas, "PWR ENDF/B-VII Cross-Section Libraries for ORIGEN-ARP," Nuclear Technology 183(3), 436-445 (2013).

R. Kelly and D. Ilas, "Verification of a Depletion Model in SCALE for the Advanced High Temperature Reactor," Nuclear Technology 183(3), 391-397 (2013).

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," Nuclear Technology 183(3), 331-340 (2013).

D. Ilas, "SCALE Code Validation for Prismatic High-Temperature Gas-Cooled Reactors," Nuclear Technology 183(3), 379-390 (2013).

W. R. Hix et al., "Core-collapse Supernovae," PoS - Proceedings of Science 148, 19 (2013).

D. G. Bowen and C. V. Parks, "Bases and Guidance on Fissile Material Exemption and General Licenses in 10 CFR Part 71," Proc. PATRAM 2013, San Francisco, Calif., August 18-23, 2013.

J. S. Scaglione et al., "Integrated Data and Analysis System for Commercial Used Nuclear Fuel Safety Assessments," Proc. PATRAM 2013, San Francisco, Calif., August 18-23, 2013.

J.-A. J. Wang et al., "Reversible Bending Fatigue Test System for Investigating Vibration Integrity of Spent Nuclear Fuel during Transportation," Proc. PATRAM 2013, San Francisco, Calif., August 18-23, 2013.

J. M. Scaglione et al., "Consequence Analysis of Spent Nuclear Fuel Reconfiguration Scenarios," Proc. PATRAM 2013, San Francisco, Calif., August 18-23, 2013.

W. J. Marshall and J. C. Wagner, "Additional Studies of the Criticality Safety of Failed Used Nuclear Fuel," Proc. PATRAM 2013, San Francisco, Calif., August 18-23, 2013.

W. J. Marshall and J. C. Wagner, "Consequences of Used Nuclear Fuel Failure on Criticality Safety," Proc. PATRAM 2013, San Francisco, Calif., August 18-23, 2013.

J. L. Powers et al., Fully Ceramic Microencapsulated (FCM) Replacement Fuel for LWRs, ORNL/TM-2013/173, Oak Ridge National Laboratory, Oak Ridge, Tenn., July 2013.

Y. Katoh et al., Status of Silicon Carbide Joining and Irradiation Studies, ORNL/TM-2013/273, Oak Ridge National Laboratory, Oak Ridge, Tenn., July 2013.

R. A. Kisner et al., Evaluation of Manufacturability of Embedded Sensors and Controls with Canned Rotor Pump System, ORNL/TM-2013/269, Oak Ridge National Laboratory, Oak Ridge, Tenn., July 2013.

T. J. Harrison, R. E. Hale, and R. J. Moses, "Economic Analysis of Advanced SMRs," Nuclear Hybrid Energy Systems 2013 Workshop, Idaho Falls, Idaho, July 24-25, 2013.

B. Radhakrishnan, S. B. Gorti, and K. T. Clarno, "Co-evolution of Microstructure and Mechanical Properties in Structural Alloys - Case Studies," Proc. 12th US National Congress on Computational Mechanics, Raleigh, NC, July 22-25, 2013.

C. M. Perfetti and B. T. Rearden, "Development of a SCALE Tool for Continuous-Energy Eigenvalue Sensitivity Coefficient Calculations," ORNL 1st Annual Postdoc Symposium, Oak Ridge, Tenn., July 18, 2013.

T. M. Pandya, "Continuous-Energy Monte Carlo Radiation Transport Validation of Shift," ORNL 1st Annual Postdoc Symposium, Oak Ridge, Tenn., July 18, 2013.

J. L. McDuffee, "Heat Transfer Through Small Moveable Gas Gaps in a Multi-Body System Using the ANSYS Finite Element Software," ASME 2013 Summer Heat Transfer Conference, Minneapolis, Minn., July 14-19, 2013.

J. R. Younkin, J. A. March-Leuba, and J. R. Garner, "A Robust and Flexible Design for GCEP Unattended Online Enrichment Monitoring: An OLEM Collection Node Network," INMM 54th Annual Meeting, Palm Desert, Calif., July 14-18, 2013.

D. Wang, B. J. Ade, and A. Ward, Cross Section Generation Guidelines for TRACE-PARCS, ORNL/TM-2012/518, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 2013.

B. B. Bevard and H. J. Smith, Core Average (MOX/LEU) Nuclide Ratios for Sequoyah and Browns Ferry Reactors (Non-Proprietary), ORNL/TM-2013/90, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 2013.

K. C. Bledsoe, M. A. Jessee, and J. A. Favorite, "Generalized Linear Least-Squares for Uncertainty Analysis in Inverse Transport Problems," Proc. 2013 American Nuclear Society Annual Meeting, Atlanta, Ga., June 16-20, 2013.

S. W. Mosher and S. R. Johnson, "ADVANTG Tutorial," Proc. 2013 American Nuclear Society Annual Meeting, Atlanta, Ga., June 16-20, 2013.

T. M. Miller and D. E. Peplow, "Corrected User Guidance to Perform Three-Dimensional Criticality Accident Alarm System Modeling with SCALE," Proc. 2013 American Nuclear Society Annual Meeting, Atlanta, Ga., June 16-20, 2013.

R. H. Howard, J. L. McDuffee, and Y. Katoh, "Graphite Compressive Creep Capsule Design for Irradiation in the HFIR," Proc. 2013 American Nuclear Society Annual Meeting, Atlanta, Ga., June 16-20, 2013.

D. E. Peplow, A. M. Ibrahim, and R. E. Grove, "Propagation of Uncertainty from a Source Computed with Monte Carlo," Proc. 2013 American Nuclear Society Annual Meeting, Atlanta, Ga., June 16-20, 2013.

R. J. Ellis, "Irradiation of U-Zr Samples in the High Flux Isotope Reactor: Reactor Physics and Isotopics Calculations," Proc. 2013 American Nuclear Society Annual Meeting, Atlanta, Ga., June 16-20, 2013.

J. J. Carbajo and J. L. McDuffee, "RELAP5 Model of a Two-phase ThermoSyphon Experimental Facility for Fuels and Materials Irradiation," Proc. 2013 American Nuclear Society Annual Meeting, Atlanta, Ga., June 16-20, 2013.

A. M. Ibrahim, D. E. Peplow, R. E. Grove, and J. C. Wagner, "Novel Hybrid Monte Carlo/Deterministic Technique for Shutdown Dose Rate Calculations," Proc. 2013 American Nuclear Society Annual Meeting, Atlanta, Ga., June 16-20, 2013.

J. L. McDuffee, D. K. Felde, L. J. Ott, and K. R. Robb, "A Two-phase Thermosyphon Experimental Facility for Fuels and Materials Irradiation," Proc. 2013 American Nuclear Society Annual Meeting, Atlanta, Ga., June 16-20, 2013.

N. Pokhriyal, J. J. Billings, U. Mertyurek, and A. T. Godfrey, "Anomaly Detection for High Fidelity Core Simulations," Proc. 2013 American Nuclear Society Annual Meeting, Atlanta, Ga., June 16-20, 2013.

D. E. Peplow, A. M. Ibrahim, and R. E. Grove, "Propagation of Uncertainty from a Source Computed with Monte Carlo," Proc. 2013 American Nuclear Society Annual Meeting, Atlanta, Ga., June 16-20, 2013.

K. C. Bledsoe, M. A. Jessee, and J. A. Favorite, "Application of Generalized Linear Least-Squares for Uncertainty Quantification in Inverse Transport Problems," Proc. 2013 American Nuclear Society Annual Meeting, Atlanta, Ga., June 16-20, 2013.

L. C. Leal, Y. Danon, D. Williams, and M. Jandel, "235U Resolved Resonance Evaluation for Benchmark Calculations in the Intermediate Energy Region," Proc. 2013 American Nuclear Society Annual Meeting, Atlanta, Ga., June 16-20, 2013.

N. M. George, K. A. Terrani, and J. J. Powers, Neutronic analysis of candidate accident-tolerant iron alloy cladding concepts, ORNL/TM-2013/121, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2013.

O. A. Omitaomu et al., "Identifying Potential Areas for Siting Interim Nuclear Waste Facilities Using Map Algebra and Optimization Approaches," Industrial and Systems Engineering Research Conference, May 18-22, 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.

Q. Lv et al., "Scaling Analysis for the Direct Reactor Auxillary Cooling System for AHTRS," Proc. 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), Pisa, Italy, May 12-15, 2013.

E. Hardin et al., "DPC Direct Disposal Feasibility Evaluation Concept Development and Analysis," NEI Used Fuel Management Conference, St. Petersburg, Fla., May 7-9, 2013.

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

C. M. Perfetti and B. T. Rearden, "Continuous-Energy Eigenvalue Sensitivity Coefficient Calculations in TSUNAMI-3D," Proc. International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering (M&C 2013), Sun Valley, Idaho, May 5-9, 2013.

S. R. Johnson, "Fast Mix Table Construction for Material Discretization," Proc. International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering (M&C 2013), Sun Valley, Idaho, May 5-9, 2013.

A. M. Ibrahim et al., "Automatic Mesh Adaptivity for CADIS and FW-CADIS Neutronics Modeling of Difficult Shielding Problems," Proc. International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering (M&C 2013), Sun Valley, Idaho, May 5-9, 2013.

D. E. Peplow, "Comparison of Hybrid Methods for Global Variance Reduction in Shielding Calculations," Proc. International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering (M&C 2013), Sun Valley, Idaho, May 5-9, 2013.

J. J. Jarrell, T. M. Evans, and G. G. Davidson, "Discrete Ordinate Quadrature Selection for Reactor-based Eigenvalue Problems," Proc. International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering (M&C 2013), Sun Valley, Idaho, May 5-9, 2013.

S. Hamilton et al., "Multiphysics Simulations for LWR Analysis," Proc. International Conference 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, "A New Approach for Modeling and Analysis of Molten Salt Reactors Using SCALE," Proc. International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering (M&C 2013), Sun Valley, Idaho, May 5-9, 2013.

W. D. Pointer, "The Next Generation Nuclear Engineer: A Vision for a New Era of Computer Aided Engineering," Proc. International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering (M&C 2013), Sun Valley, Idaho, May 5-9, 2013.

N. Pokhriyal, U. Mertyurek, A. T. Godfrey, and J. J. Billings, "Knowledge Discovery from Nuclear Reactor Simulation Data," Proc. International Workshop on Analytics for Cyber-physical Systems: Held in conjuction with SIAM Data Mining 2013, Austin, Tex., May 2, 2013.

Y. Bang, H. Abdel-Khalik, M. A. Jessee, and U. Mertyurek, "Hybrid Reduced Order Modeling for Assembly Calculations," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albquerque, N. Mex., April 28-May 2, 2013.

Y. Yan et al., "Observation and Mechanism of Hydride in Zircaloy-4 and Local Hydride Re-orientation Induced by High Pressure at High Temperatures," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

Y. Yan et al., "Observation and Mechanism of Hydride in Zircaloy-4 and Local Radial Hydride Induced by High Pressure at High Temperatures," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

B. Radhakrishnan, S. B. Gorti, K. T. Clarno, and Y. Yan, "Phase Field Simulations of Hydride Reorientation in Zircaloys," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

A. M. Bevill, G. Radulescu, J. M. Scaglione, and R. L. Howard, "ADVANTG Shielding Analysis for Closure Operations in an Open-Mode Repository," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

Wang, J.-A. et al., "SNF Test System for Bending Stiffness and Vibration Integrity," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

J. L. Peterson, "Data Mining to Determine Inventory Characteristics of UNF for Potential Future Recycling Campaigns," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

W. J. Marshall and J. C. Wagner, "Consequences of Used Nuclear Fuel Failure on Criticality Safety," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

M. Nutt et al., "Used Fuel Management System Architecture and Interface Analyses," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

J. M. Scaglione et al., "Integrating Data and Analysis Capabilities for Cask-Specific Safety Evaluations," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

R. L. Howard et al., "A Modular Design Concept for Spent Nuclear Fuel Repackaging Facility," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

R. L. Howard et al., "Production of Simulated High-Burnup Used Fuel Cladding in the HFIR," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

J. C. Wagner et al., "Assessment of Used Nuclear Fuel Inventory Relative to Disposition Options," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

R. L. Howard et al., "Preliminary Used Fuel Management System Concept of Operations," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

A. S. Blackwell et al., "Observation and mechanism of local hydrids re-orientation induced by high pressure at high temperature," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

W. J. Marshall and J. C. Wagner, "Consequence of Used Nuclear Fuel Failure on Criticality Safety," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

J. M. Scaglione, "Integrating ata and Analysis Capabilities for Cask-Specific Safety Evaluations," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

J. M. Scaglione, A. Caswell, and G. Radulescu, "Considerations for an Integrated Storage, Transportation, and Disposal Canister," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex, April 28-May 2, 2013.

J. C. Wagner et al., "Assessment of Used Nuclear Fueld Inventory Relative to Disposition Options," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

M. Nutt et al., "Used Fuel Management System Architecture and Interface Analyses," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex, April 28-May 2, 2013.

E. Hardin et al., "SNF Disposal Concepts for Small and Large Waste Packages," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex, April 28-May 2, 2013.

A. Worrall, "Utilization of Used Nuclear Fuel (UNF) in a Potential Future US Fuel Cycle Scenario," Proc. 2013 International High-Level Radioactive Waste Management (2013) IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

A. M. Bevill, J. M. Scaglione, and R. L. Howard, "ADVANTG Shielding Analysis for Closure Operations in an Open-Mode Repository," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuqerque, N. Mex., April 28-May 2, 2013.

J.-A. J. Wang et al., "Test System for Evaluating Spent Nuclear Fuel Bending Stiffness and Vibration Integrity," Proc. 2013 International High-Level Radioactive Waste Management (2013 IHLWRM), Albuquerque, N. Mex., April 28-May 2, 2013.

T. J. Harrison, R. E. Hale, and R. J. Moses, Status Report on Modeling and Analysis of Small Modular Reactor Economics, ORNL/TM-2013/138, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2013.

B. 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., April 2013.

D. A. Clayton and W. P. Poore, III, Fukushima Daiichi - A Case Study for BWR Instrumentation and Control Systems Performance during a Severe Accident, ORNL/TM-2013/154, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2013.

K. V. Gilligan, B. L. Kirk, and M. J. Whitaker, Oak Ridge National Laboratory Next-Generation Safeguards Initiative: Human Capital Development, ORNL/TM-2012/539, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2013.

D. E. Peplow, T. M. Miller, B. W. Patton, and J. C. Wagner, "Hybrid Monte Carlo/Deterministic Methods for Accelerating Active Interrogation Modeling," Nuclear Technology, 182(1), pp. 63-74 (April 2013).

J. J. Billings et al., "Technical Spotlight: Modeling and Simulation Made NICE," NEAMS Update Quarterly Report for October - December 2012, ANL/NEAMS-13/1, Argonne National Laboratory, Argonne, Ill., March 2013.

H. J. Smith, I. C. Gauld, and U. Mertyurek, Analysis of Experimental Data for High Burnup BWR Spent Fuel Isotopic Validation - SVEA-96 and GE14 Assembly Designs, ORNL/TM-2013/18, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2013.

W. P. Poore, III, R. Belles, G. T. Mays, and O. A. Omitaomu, Evaluation of Suitability of Selected Set of Department of Defense Military Bases and Department of Energy Facilities for Siting a Small Modular Reactor, ORNL/TM-2013/118, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2013.

R. Belles et al., Evaluation of Suitability of Selected Set of Coal Plant Sites for Repowering with Small Modular Reactors, ORNL/TM-2013/109, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2013.

J. J. Billings et al., "Simulate This! - The Eclipse Platform as an Integrated Computational Environment," EclipseCon 2013, Boston, Mass., March 25-28, 2013.

K. A. Terrani et al., "Advanced Oxidation Resistant Iron Alloys as LWR Fuel Cladding," Enlarge Halden Program Group (EHPG) 2013, Gol, Norway, March 10, 2013.

M. L. Williams, G. Ilas, W. J. Marshall, and B. T. Rearden, "Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization," International Conference on Nuclear Data for Science and Technology (ND2013), New York, NY, March 4-8, 2013.

M. T. Pigni, L. C. Leal, M. E. Dunn, and K. H. Guber, "Evaluation of Tungsten Neutron Cross Sections in the Resolved Resonance Region," International Conference on Nuclear Data for Science and Technology (ND2013), New York, NY, March 4-8, 2013.

K. H. Guber et al., "Neutron-Induced Cross Sections Measurements of Calcium," International Conference on Nuclear Data for Science and Technology (ND2013), New York, NY, March 4-8, 2013.

I. J. Thompson, J. E. Escher, and G. Arbanas, "Coupled-Channel Models of Direct-Semidirect Capture via Giant-Dipole Resonances," International Conference on Nuclear Data for Science and Technology (ND2013), New York, NY, March 4-8, 2013.

I. J. Thompson and G. Arbanas, "Coupled-channel treatment of Isobaric Analog Resonances in (p,p') Capture Processes," International Conference on Nuclear Data for Science and Technology (ND2013), New York, NY, March 4-8, 2013.

G. Arbanas, M. E. Dunn, and M. L. Williams, "Inverse Sensitivity/Uncertainty Methods Development for Nuclear Fuel Cycle Applications," International Conference on Nuclear Data for Science and Technology (ND2013), New York, NY, March 4-8, 2013.

W. D. Pointer et al., "Developing a Comprehensive Software Suite for Advanced Reactor Performance and Safety Analysis," 2013 IAEA Conference on Fast Reactors, Paris, France, March 4-7, 2013.

M. A. Okuniewski et al., "Microstructural Evolution of a Uranium-Zirconium Alloy at Low Fluences," 2013 TMS Annual Meeting & Exhibition, San Antonio, Tex., March 3-7, 2013.

D. Mueller, J. M. Scaglione, and J. C. Wagner, Computational Benchmark and Estimated Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit, ORNL/TM-2012/96, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2013.

D. Mueller, W. J. Marshall, and J. M. Scaglione, Review and Prioritization of Technical Issues Related to Burnup Credit for BWR Fuel, ORNL/TM-2012/261, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2013.

J. McFarlane et al., Phenylnapthalene Derivatives as Heat Transfer Fluids for Concentrating Solar Power: Loop Experiments and Final Report, ORNL/TM-2013/26, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2013.

K. R. Robb, M. T. Farmer, and M. W. Francis, Enhanced Ex-Vessel Analysis for Fukushima Daiichi Unit 1: Melt Spreading and Core-Concrete Interaction Analyses with MELTSPREAD & CORQUENCH, ORNL/TM-2012/455, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2013.

C. M. Hopper, Domestic and International Nuclear Energy Voluntary Consensus Standards Needs, ORNL/TM-2012/607, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2013.

W. J. Marshall and B. T. Rearden, Criticality Safety Validation of SCALE 6.1, ORNL/TM-2012/578, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2013.

R. T. Jubin et al., "Impact of Storage Time on the Needed Capture Efficiency for Volatile Radionuclides," Waste Management 2013, Phoenix, Ariz., February 24-28, 2013.

Z. Li et al., "Regulatory Perspective on Potential Fuel Reconfiguration and Its Implication to High Burnup Spent Fuel Storage and Transportation," Waste Management 2013, Phoenix, Ariz., February 24-28, 2013.

J. C. Wagner et al., "Categorization of Used Nuclear Fuel Inventory in Support of a Comprehensive National Nuclear Fuel Cycle Strategy," Waste Management 2013, Phoenix, Ariz., February 24-28, 2013.

M. Nutt et al., "Used Fuel Management System Interface Analyses," Waste Management 2013, Phoenix, Ariz., February 24-28, 2013.

J. C. Wagner, "Categorization of Used Nuclear Fuel Inventory in Support of a Comprehensive National Nuclear Fuel Cycle," Waste Management 2013, Phoenix, Ariz., February 24-28, 2013.

A. Worrall, "Utilization of Used Nuclear Fuel (UNF) in a Potential Future US Fuel Cycle Scenario," Waste Management 2013, Phoenix, Ariz., February 24-28, 2013.

C. L. Britton et al., Johnson Noise Thermometry System Requirements, ORNL/TM-2013/22, Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2013.

D. E. Holcomb, "The United States Fluoride Salt Cooled High Temperature Reactor Program," Conference on Molten Salts in Nuclear Technology (CMSNT-2013), Mumbai, India, January 9-11, 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, January 9-11, 2013.