2012 Publications
Author(s) / Report Title / Publication Number / Date
A. M. Bevill, S. R. Johnson, S. W. Mosher, and J. O. Johnson, ADVANTG Improvements and New Capabilities, ORNL/LTR-2012/486, Oak Ridge National Laboratory, Oak Ridge, Tenn. (2012)
D. Ilas, Impact of HFIR LEU Conversion on Spectral Characteristics of Experimental Locations, ORNL/LTR-2012/414, Oak Ridge National Laboratory, Oak Ridge, Tenn. (2012)
G. Radulescu and J. C. Wagner, Burnup Credit Criticality Benchmark, Phase VII, UO2 Fuel: Study of Spent Fuel Compositions for Long-term Disposal, Nuclear Energy Agency, 2012.
D. E. Peplow and K. C. Bledsoe, NA-42 TI ORNL12-108J: Advanced Multi-Dimensional Forward and Inverse Modeling Annual Report, ORNL/LTR-2012-402, Oak Ridge National Laboratory, Oak Ridge, Tenn. (2012)
G. Ilas, I. C. Gauld, and G. Radulescu, "Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE," Annals of Nuclear Energy 46(1), 43-55 (2012).
J. M. Scaglione, A. Caswell, and G. Radulescu, End-of-Year Status Report on Integrated Canister Design and Evaluation, ORNL/LTR-2012/448, Oak Ridge National Laboratory, Oak Ridge, Tenn., 2012.
T. M. Rosseel, D. J. Naus, and I. Remec, "DOE LWRS/EPRI - LTO Research Plans on the Effects of Radiation on Concrete," presented in Tokyo, Japan, November 15, 2012.
C. G. Baker et al., "High Performance Radiation Transport Simulations: Preparing for TITAN," SC12 Supercomputing, Salt Lake City, Utah, November 12-15, 2012.
J. E. Banfield, S. P. Hamilton, K. T. Clarno, and G. I. Maldonado, "A New Semi-Implicit Direct Kinetics Method with Analytical Representation of Delayed Neutrons," Proc. 2012 ANS Winter Meeting and Nuclear Technology Expo, San Diego, Calif., November 11-15, 2012.
A. M. Ibrahim et al., "Automatic Mesh Adaptivity for Hybrid Monte Carlo/Deterministic Neutronics Modeling of Difficult Shielding Problems," Proc. 2012 ANS Winter Meeting and Nuclear Technology Expo, San Diego, Calif., November 11-15, 2012.
C. M. Perfetti and B. T. Rearden, "Data Adjustment Exercises for Fast Reactor Benchmark Problems Using SCALE," Trans. Am. Nucl. Soc., 107, 624-627 (2012).
C. M. Perfetti, "Advanced Methods for Eigenvalue Sensitivity Coefficient Calculations," Trans. Am. Nucl. Soc., 107, 575-578 (2012).
I. Remec, "Towards Estimates of Neutron Fluence in Biological Shield of Zion 1&2 and Ginna PWRs," Concrete Irradiation Damage Working Group, Charlotte, NC, October 3, 2012.
G. Radulescu, H. J. Smith, D. Ilas, and R. A. Lefebvre, A Comprehensive Database and Automation Tool for Used Nuclear Fuel Safety Analyses, ORNL/LTR-2012/469, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2012.
M. Monterial et al., "Automating the Coupling of ORIGEN with GADRAS via the Fallout Analysis Tool for National Technical Nuclear Forensics," INMM 53rd Annual Meeting, Orlando, Fla., July 15-19, 2012.
J. C. Wagner et al., "Burnup Credit Code Validation," presented in Washington, D.C., July 10, 2012.
D. E. Peplow and L. Wetzel, "Methods for Detector Placement and Analysis of Criticality Accident Alarm Systems,"Trans. Am. Nucl. Soc. 106, 597-500 (2012).
S. Goluoglu, K. B. Bekar, and D. Wiarda, "SCALE Continuous-Energy Monte Carlo Depletion with Parallel KENO in TRITON," Trans. Am. Nucl. Soc. 106, 723-725 (2012).
A. M. Bevill and S. W. Mosher, "A New Source Biasing Approach in ADVANTG," Trans. Am. Nucl. Soc. 106, 350-353 (2012).
D. E. Peplow, "Methods for Detector Placement and Analysis of Criticality Accident Alarm Systems," 2012 American Nuclear Society Annual Meeting, Chicago, Ill., June 24-28, 2012.
I. Remec, "Estimation of Radiation Fields in PWR Biological Shield for Assessing Radiation Effects on Concrete," presented at the Concrete Irradiation Damage Working Group Meeting, Chicago, Ill., June 27, 2012.
K. C. Bledsoe, M. A. Jessee, and J. A. Favorite, "Uncertainty Quantification for Inverse Transport Methods," presented on May 3, 2012, Las Vegas, Nev.
D. E. Peplow, Preliminary Demonstration of Software to Generate Importance Maps, ORNL/LTR-2012/163, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2012.
K. C. Bledsoe, Development of Uncertainty Analysis Software, ORNL/LTR-2012/165, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2012.
K. C. Bledsoe, Preliminary Demonstration of Inverse Algorithms Software, ORNL/LTR-2012/165, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2012.
G. Radulescu et al., An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses - Isotopic Composition Predictions, ORNL/TM-2011/509, NUREG/CR-7108, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2012.
R. Slaybaugh, T. M. Evans, and G. G. Davidson, and P. Wilson, "Rayleigh Quotient Iteration in 3D, Deterministic Neutron Transport," Proc. PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)
B. T. Rearden et al., "Enhancements in SCALE 6.1," Proc. PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)
S. P. Hamilton et al., "Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations," Proc. PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)
C. M. Perfetti et al., "Determining Importance Weighting Functions for Contributon Theory Eigenvalue Sensitivity Coefficient Methodologies," Proc. PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)
D. Ilas, "Neutronics of Prismatic Fluoride Salt Cooled High Temperature Reactors," Proc. PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)
C. M. Perfetti et al., "Development of Continuous-Energy Eigenvalue Sensitivity Coefficient Calculation Methods in the Shift Monte Carlo Code," Proc. PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)
B. T. Mervin et al., "Variance Estimation in Domain Decomposed Monte Carlo Eigenvalue Calculations," Proc. PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)
N. Sly et al., "Verification of the Shift Monte Carlo Code," Proc. PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)
A. Ibrahim et al., "Acceleration of Monte Carlo Criticality Calculations Using Deterministic-Based Starting Sources," Proc. PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)
J. Jarrell et al., "Full Core Reactor Analysis: Running Denovo on Jaguar," Proc. PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)
A. T. Cisneros and D. Ilas, "Neutronics and Depletion Methods for Parametric Studies of Fluoride Salt Cooled High Temperature Reactors with Slab Fuel Geometry and Multi-Batch Fuel Management Schemes," Proc. PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)
D. Ilas, D. E. Holcomb, and V. K. Varma, "Advanced High Temperature Reactor Neutronic Core Design," Proc. PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)
D. Ilas, "SCALE Code Validation for Prismatic High-Temperature Gas-Cooled Reactors," Proc. PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)
R. Kelly and D. Ilas, "Verification of a Depletion Method in SCALE for the Advanced High Temperature Reactor," Proc. PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2012)
D. Ilas, Development of a Scale Model for High Flux Isotope Reactor Cycle 400, ORNL/TM-2011/367, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2012.
B. Philip, K. T. Clarno, R. S. Sampath, M. A. Berrill, G. Dilts, S. P. Hamilton, S. Allu, P. Barai, and J. E. Banfield, "A Jacobian Free Newton Krylov Method with Multilevel Block Preconditioning for Multi-Domain Quasistatic Thermomechanics," presented at the Twelfth Copper Mountain Conference on Iterative Methods, Copper Mountain, Colo., March 28, 2012.
K. T. Clarno, S. P. Hamilton, B. Philip, M. A. Berrill, R. S. Sampath, S. Allu, D. Pugmire, G. Dilts, and J. E. Banfield, Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations, ORNL/TM-2012/33, Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2012.
