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Reactor and Nuclear Systems 2013 Publications


The following collection of publications stem from current and former ORNL staff members, in addition to external collaborators, in an attempt to capture historical reactor and nuclear systems projects and research. Other historical documents which are included emphasize significant research in other areas of expertise.

2013 Publications

 

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, pp. 276-292 (2013).

J. Hu et al., “Isotopic Impacts on the Performance of Self-Interrogation Neutron Resonance Densitometry for Spent Fuel Assay,” Nuclear Science and Engineering 729, pp. 247-253 (2013).

H. Yin et al., "Mixtures of SF6 - CO2 as working fluids for geothermal power plants," Applied Energy 106(6), p. 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, p. 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, pp. 201-213 (2013).

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

C. McGraw and G. Ilas, "PWR ENDF/B-VII Cross-Section Libraries for ORIGEN-ARP," Nuclear Technology 183(3), pp. 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), pp. 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), pp. 331-340 (2013).

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

J. J. Jarrell, A. T. Godfrey, T. M. Evans, and G. G. Davidson, “Full Core Reactor Analysis: Running Denovo on Jaguar,” Nuclear Science and Engineering 175(3), pp. 283-291 (2013).

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

B. R. Grogan et al., “Investigation of Active Interrogation Techniques to Detect Special Nuclear Material in Maritime Environments:  Boarded Search of a Cargo Container Ship,” Nuclear Instruments and Methods in Physics Research Section B:  Beam Interactions with Materials and Atoms 316, p. 62 (2013).

T. M. Miller et al., “Investigation of Active Interrogation Techniques to Detect Special Nuclear Material in Maritime Environments:  Standoff Interrogation of Small and Medium Sized Cargo Ships,” Nuclear Instruments and Methods in Physics Research Section B:  Beam Interactions with Materials and Atoms 316(1), pp. 94-104 (2013).

Y. Yan et al., “Ductility Evaluation of As-Hydrided and Hydride Reoriented  Zircaloy-4 Cladding under Simulated Dry-Storage Condition,” 2013 MRS Fall Meeting, Boston, Mass., December 1-6, 2013.

D. E. Holcomb et al., Fluoride Salt-Cooled High-Temperature Reactor Technology Development and Demonstration Roadmap, ORNL/TM-2013/401, Oak Ridge National Laboratory, Oak Ridge, Tenn., November 2013.

S. W. Mosher et al., ADVANTG – An Automated Variance Reduction Parameter Generator, ORNL/TM-2013/416, Oak Ridge National Laboratory, Oak Ridge, Tenn., November 2013.

J. C. Gehin and I. G. Maldonado.  Preface.  In Special Issue on the PHYSOR 2012 International Conference on the Physics of Reactors, Nuclear Science and Engineering (NSE), Knoxville, Tenn., November 2013.

I. C. Gauld et al., “Integral Testing of the 239Np Capture Cross Section using Reactor Experiments,” Cross Section Evaluation Working Group Meeting (CSEWG), Upton, NY, November 17-21, 2013.

K. C. Bledsoe and J. A. Favorite, “Improved Differential Evolution Implementation for Solving Inverse Transport Problems,” Trans. Am. Nucl. Soc. 109(1),781-784 (2013).  

J. L. Narvaez, M. R. Bradisse, and K. R. Robb, “Design Concept for Rabbit Irradiation in the RB* Position of HFIR,” Proc. American Nuclear Society Winter Meeting and Nuclear Technology Expo, November 10-14, 2013.

J. J. Powers et al., “Reactor Physics Analysis of Thorium Fuel Cycles Using Molten Salt Reactors,” Trans. Am. Nucl. Soc. 109(1),1457-1460 (2013). 

D. G. Bowen and N. Brown, “A Revision to ANS-8.1 “Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors,” Trans. Am. Nucl. Soc. 109(1),878-880 (2013). 

C. M. Perfetti and B. T. Rearden, “A New Method for Calculating Generalized Response Sensitivities in Continuous-Energy Monte Carlo Applications in SCALE,” Trans. Am. Nucl. Soc. 109(1), 739-742 (2013).

I. Remec et al., “Concrete Aging and Degradation in NPPs:  LWRs Program R&D Progress Report,” Trans. Am. Nucl. Soc. 109(1), 403-406 (2013).

M. A. Jessee, W. A. Wieselquist, M. L. Williams, and K. S. Kim, “VERA Benchmark Calculations using the SCALE-Polaris Lattice Physics Code,” Trans. Am. Nucl. Soc. 109(1), 1413-1415 (2013).

V. Sobes, L. C. Leal, and B. Forget, “Coupled Differential and Integral Data Analysis for Improved Uncertainty Quantification,” Trans. Am. Nucl. Soc. 109(1), 857-860 (2013).

G. Arbanas et al., “Integral Benchmark Experiments in the Inverse Sensitivity/Uncertainty Computations,” Trans. Am. Nucl. Soc. 109(1), 808-811 (2013).

V. B. Khane and P. K. Jain, “Steady State COMSOL Thermal-Hydraulics Models for ORNL’s High Flux Isotope Reactor,” Trans. Am. Nucl. Soc. 109(1), 1649-1651 (2013).

B. A. Khuwaileh et al., “The Effect of Implicit Self-Shielding on the Inverse Sensitivity/Uncertainty Method for Thermal Reactors,” Trans. Am. Nucl. Soc. 109(1), 804-807.

M. Fratoni et al., “Assessment of once-through Thorium Fuel Cycles in Subcritical Systems Driven by a Fusion-Fission Hybrid,” Trans. Am. Nucl. Soc. 109(1),1461-1464 (2013). 

N. M. George, K. A. Terrani, and J. J. Powers, “Neutronic Analysis of Candidate Accident-tolerant Iron Alloy Cladding Concepts,” Trans. Am. Nucl. Soc. 109(1),1506-1508 (2013). 

B. T. Rearden et al., “SCALE and AMPX Advancement to Support NCS Applications,” Trans. Am. Nucl. Soc. 109(1), 907-910 (2013).

R. J. Ellis, “Reactor Physics Analysis of HWR Fuel Cycle Options,” Trans. Am. Nucl. Soc. 109(1), 1472-1475 (2013).

J. J. Powers et al., “Reactor Physics Analysis of Thorium Fuel Cycles Using Molten Salt Reactors” Trans. Am. Nucl. Soc. 109(1), 1457-1460 (2013). 

G. T. Mays et al., “Application of Spatial Data Modeling and Geographical Information Systems (GIS) for Identification of Potential Siting Options for Small Modular Reactors,” Trans. Am. Nucl. Soc. 109(1),2241-2244 (2013). 

L. C. Leal et al., “Overview of the Resonance Evaluations for 16O, 56Fe, 235U, and 239Pu for the CIELO Project,” NEMEA-7 International Collaboration on Nuclear Data, Geel, Belgium, November 5-8, 2013.

L. C. Leal et al., “Resonance Evaluations of 235Ufor the CIELO Project,” NEMEA-7 International Collaboration on Nuclear Data, Geel, Belgium, November 5-8, 2013.

L. C. Leal et al., “Resonance Evaluations for 56Fe and 16O for the CIELO Project,” NEMEA-7 International Collaboration on Nuclear Data, Geel, Belgium, November 5-8, 2013.

D. Ilas, Impact of HFIR LEU Conversion on Beryllium Reflector Degradation Factors, ORNL/TM-2013/441, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2013.

S. Slattery, T. M. Evans, and P. Wilson, “A Multiple-Set Overlapping-Domain Decomposed Monte Carlo Synthetic Acceleration Method for Linear Systems,” Proc. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013 (SNA + MC 2013), Paris, France, October 27-31, 2013.

C. M Perfetti and B. T. Rearden, “Development of a SCALE Tool for Continuous-Energy Eigenvalue Sensitivity Coefficient Calculations,” Proc. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013 (SNA + MC2013), Paris, France, October 27-31, 2013.

M. H. Piro et al., “High Temperature Thermochemical and Isotopic Simulations of High Burnup UO2 Fuel,” Proc. Materials Modeling and Simulation for Nuclear Fuels (MMSNF) 2013 Workshop, Chicago, Ill., October 14-16, 2013.

J. D. Freels, P. K. Jain, and C. J. Hurt, “Investigation of Thermal Contact Gas Gap Conductions Using COMSOL Multiphysics,” COMSOL Conference, Boston, Mass., October 9-12, 2013.

D. Wang, P. K. Jain, and J. D. Freels, “Application of COMSOL Pipe Flow Module to Develop a High Flux Isotope Reactor (HFIR) System Loop Model,” COMSOL Conference, Boston, Mass., October 9-12, 2013.

T. M. Miller and D. E. Peplow, Guide to Performing Computational Analysis of Criticality Accident Alarm Systems, ORNL/TM-2013/211, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2013.

V. Koritarov et al., Energy Zones Study:  A Comprehensive Web-Based Mapping Tool to Identify and Analyze Clean Energy Zones in the Eastern Interconnection, ANL/DIS-13/09, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2013.

G. L. Bell et al., Fabrication and Irradiation of Depleted Uranium UO2 Disks, ORNL/TM-2013/344, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2013.

J. J. Powers et al., “Parametric Analyses of Single-zone Thorium-fueled Molten Salt Reactor Fuel Cycle Options,” GLOBAL 2013: International Nuclear Fuel Cycle Conference, Salt Lake City, Utah, September 29-October 3, 2013.

J. J. Powers et al., “Assessment of Fuel Cycle Options for a Single-Zone Thorium MSR,” GLOBAL 2013:  International Nuclear Fuel Cycle Conference, Salt Lake City, Utah, September 29-October 3, 2013.

A. M. Ibrahim et al., “Hybrid Technique in SCALE for Fission Source Convergence Applied to Used Nuclear Fuel Analysis,” Proc. NCSD 2013 – Criticality Safety in the Modern Era:  Raising the Bar, Wilmington, NC, September 29-October 3, 2013.

B. T. Rearden et al., “Overview of SCALE 6.2,” Proc. NCSD 2013 – Criticality Safety in the Modern Era: Raising the Bar, Wilmington, NC, September 29-October 3, 2013.

W. A. Wieselquist, K. S. Kim, G. Ilas, and I. C. Gauld, “Comparison of Burnup Credit Uncertainty Quantification Methods,” Proc. NCSD 2013 – Criticality Safety in the Modern Era: Raising the Bar, Wilmington, NC, September 29-October 3, 2013.

C. M. Perfetti and B. T. Rearden, “Use of SCALE Continuous-Energy Monte Carlo Tools for Eigenvalue Sensitivity Coefficient Calculations,” Proc. NCSD 2013 – Criticality Safety in the Modern Era:  Raising the Bar, Wilmington, NC, September 29-October 3, 2013.

K. B. Bekar et al., “Enhancements in Continuous-Energy Monte Carlo Capabilities in SCALE,” Proc. NCSD 2013 – Criticality Safety in the Modern Era:  Raising the Bar, Wilmington, NC, September 29-October 3, 2013.

T. M. Miller and D. E. Peplow, “Guidance Detailing Methods to Calculate Criticality Accident Alarm System Detector Response and Coverage,” Proc. NCSD 2013 – Criticality Safety in the Modern Era:  Raising the Bar, Wilmington, NC, September 29-October 3, 2013.

T. M. Miller et al., “Benchmark Data from Experiments 2 and 3 of the 2010 Criticality Accident Alarm System Benchmark Experiments at the CEA Valduc Silene Facility,” Proc. NCSD 2013 – Criticality Safety in the Modern Era:  Raising the Bar, Wilmington, NC, September 29-October 3, 2013.

W. J. Marshall, D. Wiarda, C. Celik, and B. T. Rearden, “Validation of Criticality Safety Calculations with SCALE 6.2,” Proc. NCSD 2013 – Criticality Safety in the Modern Era:  Raising the Bar, Wilmington, NC, September 29-October 3, 2013.

W. J. Marshall and B. T. Rearden, “The SCALE Verified, Archived, Library of Inputs and Data – VALID,” Proc. NCSD 2013 – Criticality Safety in the Modern Era:  Raising the Bar, Wilmington, NC, September 29-October 3, 2013.

M. L. Williams et al., “SCALE Uncertainty Quantification Methodology for Criticality Safety Analysis of Used Nuclear Fuel,” Proc. NCSD 2013 – Criticality Safety in the Modern Era: Raising the Bar, Wilmington, NC, September 29-October 3, 2013.

G. F. Flanagan, “National and International Activities to Develop Risk Informed Performance Based Safety Standards for Sodium Cooled Fast Reactors,” American Nuclear Society International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2013, Columbia, SC, September 22-26, 2013.

A. M. Ibrahim et al., “Automatic Mesh Adaptivity for Hybrid Monte Carlo/Deterministic Neutronics Modeling of Fusion Energy Systems,” Proc. 11th International Symposium on Fusion Nuclear Technology, Barcelona, Spain, September 16-20, 2013.

A. M. Ibrahim et al., “Novel Hybrid Monte Carlo/Deterministic Technique for Shutdown Does Rate Analysis,” Proc. 11th International Symposium on Fusion Nuclear Technology, Barcelona, Spain, September 16-20, 2013.

J. J. Powers and K. A. Terrani, “Uranium Nitride:  Enabling New Applications for TRISO Fuel Particles,” Proc. 2013 LWR Fuel Performance Meeting/Top Fuel, Charlotte, NC, September 15-19, 2013.

J. J. Powers and B. D. Wirth, “Development and Demonstration of the TRIUNE TRISO Fuel Performance Model,” Proc. 2013 LWR Fuel Performance Meeting/Top Fuel, Charlotte, NC, September 15-19, 2013.

L. J. Ott et al., “Irradiation of SIC Clad Fuel Rods in the HFIR,” Proc. 2013 LWR Fuel Performance Meeting/Top Fuel, Charlotte, NC, September 15-19, 2013.

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

T. J. Harrison, “Fast Reactor Fuel Cycle Cost Estimates for Advanced Fuel Cycle Studies,” Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economics Characteristics, September 11-13, 2013.

M. S. Cetiner et al., Supervisory Control System Architecture for Advanced Small Modular Reactors, ORNL/TM-2013/320, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 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. M. 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.

C. V. Parks et al., “Overview of IAEA Modifications for Exceptions to the Requirements for Transport of Fissile Material,” 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.

J. Hu et al., "New Approach to Fork Measurement Data Analysis by RADAR-CRISP and ORIGEN Integration," 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.

M. P. Trammell et al., “Recapturing Graphite-Based Fuel Element Technology for Nuclear Thermal Propulsion,” AIAA Propulsion and Energy Event, San Jose, Calif., July 15-17, 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,” Proc. 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.

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," Trans. Am. Nucl. Soc. 108, 498-501 (2013).

R. H. Howard, J. L. McDuffee, and Y. Katoh, "Graphite Compressive Creep Capsule Design for Irradiation in the HFIR," Trans. Am. Nucl. Soc. 108, 339-342 (2013).

D. E. Peplow, A. M. Ibrahim, and R. E. Grove, "Propagation of Uncertainty from a Source Computed with Monte Carlo," Trans. Am. Nucl. Soc. 108, 643-646 (2013).

R. J. Ellis, "Irradiation of U-Zr Samples in the High Flux Isotope Reactor: Reactor Physics and Isotopics Calculations," Trans. Am. Nucl. Soc. 108, 814-816 (2013).

J. J. Carbajo and J. L. McDuffee, "RELAP5 Model of a Two-phase ThermoSyphon Experimental Facility for Fuels and Materials Irradiation," Trans. Am. Nucl. Soc. 108, 1026-1028 (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," Trans. Am. Nucl. Soc. 108, 647-650 (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," Trans. Am. Nucl. Soc. 108, 1022-1025 (2013).

B. B. Bevard, “Fuel Qualification to Support Licensing of MOX,” 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," Trans. Am. Nucl. Soc. 108, 781-784 (2013).

D. E. Peplow, A. M. Ibrahim, and R. E. Grove, "Propagation of Uncertainty from a Source Computed with Monte Carlo," Trans. Am. Nucl. Soc. 108, 643-646 (2013).

K. C. Bledsoe, M. A. Jessee, and J. A. Favorite, "Application of Generalized Linear Least-Squares for Uncertainty Quantification in Inverse Transport Problems," Trans. Am. Nucl. Soc. 108, 445-448 (2013).

L. C. Leal, Y. Danon, D. Williams, and M. Jandel, "235U Resolved Resonance Evaluation for Benchmark Calculations in the Intermediate Energy Region," Trans. Am. Nucl. Soc. 108, 495-497 (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.

D. E. Holcomb and R. T. Wood, “Advanced Small Modular Reactor R&D Program: Instrumentation, Controls, and Human-Machine Interface (ICHMI) Pathway,” Proc. International Atomic Energy (IAEA) Technical Meeting on Instrumentation and Control in Advanced Small and Medium-Sized Reactors (SMRs), Vienna, Austria, May 21-24, 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 conjunction 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), Albuquerque, 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 hydride 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, "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. 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 Fuel 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), Albuquerque, 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.

V. Sobes et al., “New Resolved Resonance Region Evaluation for 63Cu and 65Cu for Nuclear Criticality Safety Program,” 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.

L. C. Leal et al., “239Pu Resonance Evaluation for Thermal Benchmark System Calculations,” 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.

 

 

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