M. D. DeHart, S. Goluoglu, and M. E. Dunn, “KENO Continuous Energy Calculations for a Suite of Computational Benchmarks for the Doppler Reactivity Defect,” mcsna01087full.pdf in Proc. of Joint International Topical Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications (M&C + SNA2007), April 15–19, 2007, Monterey, California, on CD-ROM, American Nuclear Society, LaGrange Park, Illinois (2007).

M. D. DeHart, I. C. Gauld, and M. L. Williams, “High-Fidelity Lattice Physics Capabilities of the SCALE Code System Using TRITON,” mcsna05008full.1.pdf in Proc. of Joint International Topical Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications (M&C + SNA2007), April 15–19, 2007, Monterey, California, on CD-ROM, American Nuclear Society, LaGrange Park, Illinois (2007).

M. D. DeHart, “Simplification of Multi-Group Cross-Section Processing for Large Depletion Calculations in TRITON,” mcsna01086full.pdf in Proc. of Joint International Topical Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications (M&C + SNA2007), April 15–19, 2007, Monterey, California, on CD-ROM, American Nuclear Society, LaGrange Park, Illinois (2007).

B. T. Rearden and J. E. Horwedel, "Automatic Differentiation with Code Coupling and Applications to SCALE Modules," mcsna01317full.pdf in Proc. of Joint International Topical Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications (M&C + SNA2007), April 15–19, 2007, Monterey, California, on CD-ROM, American Nuclear Society, LaGrange Park, Illinois (2007).

C. V. Parks, J. C. Wagner, D. E. Mueller, and I. C. Gauld, “Full Burnup Credit in Transport and Storage Casks: Benefits and Implementation,” RadWaste Solutions, Vol. 14, No. 2, March/April 2007, pp. 32–41.

B. D. Murphy, ORIGEN-ARP Cross-Section Libraries for the RBMK-1000 System, ORNL/TM-2006/139, UT-Battelle, LLC, Oak Ridge National Laboratory, November 2006.

G. Ilas, I. C. Gauld, and V. J. Jodoin, “LWR Cross Section Libraries for ORIGEN-ARP in SCALE 5.1,” Trans Am. Nucl. Soc., 95, 706 (2006).

James E. Horwedel, "Automatic Differentiation to Couple SCALE Modules Using GRESS 90--Part I: Methodology," Trans. Am. Nucl. Soc., 95, 699-701 (2006).

Bradley T. Rearden and James E. Horwedel, "Automatic Differentiation to Couple SCALE Modules Using GRESS 90--Part II: Application," Trans. Am. Nucl. Soc., 95, 702-705 (2006).

Bradley T. Rearden, "A Criticality Code Validation Exercise for a LEU Lattice," Trans. Am. Nucl. Soc., 95, 381-386 (2006).

Aaron M. Fleckenstein and Bradley T. Rearden, "Multigroup Cross Section and Cross Section Covariance Data Visualization with Javapeno," Trans. Am. Nucl. Soc., 95, 292-295 (2006).

D. F. Hollenbach, L. M. Petrie, and S. M. Bowman, “Advances in the KENO-VI Geometry Package,” abstract submitted to ANS 2006 Winter Meeting “Ensuring the Future in Times of Change: Nonproliferation and Security,” November 12–16, 2006, Albuquerque, New Mexico. Trans. Am. Nucl. Soc., 95, 296–298 (2006).

James E. Horwedel, Stephen M. Bowman, and Daniel F. Hollenbach, “New Capabilities to Calculate Volumes of SCALE/KENO-VI Geometry Models,” Trans. Am. Nucl. Soc., 95, 287–289 (2006).

C. F. Weber and B. L. Broadhead, “Inverse Depletion/Decay Analysis Using the SCALE Code System,” Trans. Am. Nucl. Soc., 95, 248–249 (2006).

Mark D. DeHart, “Lattice Physics Calculations Using the TRITON Sequence of SCALE,” a workshop presented at PHYSOR–2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, September 10–14, 2006, Vancouver, British Columbia, Canada.

S. Goluoglu, "Analysis of a Computational Benchmark for a High-Temperature Reactor Using SCALE," C022.pdf in Proc. of PHYSOR–2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, September 10–14, 2006, Vancouver, British Columbia, Canada.

S. M. Bowman and D. F. Gill, “Validation of Standardized Computer Analyses for Licensing Evaluation/TRITON Two-Dimensional and Three-Dimensional Models for Light Water Reactor Fuel,” B153.pdf in Proc. of PHYSOR–2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, September 10–14, 2006, Vancouver, British Columbia, Canada.

Mark D. DeHart, “Advancements in Generalized-Geometry Discrete Ordinates Transport for Lattice Physics Calculations,” A154.pdf in Proc. of PHYSOR–2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, September 10–14, 2006, Vancouver, British Columbia, Canada.

Mark D. DeHart, “Lattice Physics Capabilities of the SCALE Code System Using TRITON,” A121.pdf in Proc. of PHYSOR–2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, September 10–14, 2006, Vancouver, British Columbia, Canada.

Mark L. Williams, Jess C. Gehin, and Kevin T. Clarno, “Sensitivity Analysis of Reactivity Responses Using One-Dimensional Discrete Ordinates and Three-Dimensional Monte Carlo Methods,” C135.pdf in Proc. of PHYSOR–2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, September 10–14, 2006, Vancouver, British Columbia, Canada.

Bryan L. Broadhead, Calvin M. Hopper, and Jehudah J. Wagschal, "Sensitivity of Adjusted Responses to Parameter and Response Uncertainties," B033.pdf in Proc. of PHYSOR–2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, September 10–14, 2006, Vancouver, British Columbia, Canada.

Ian Gauld, “Validation of ORIGEN-S Decay Heat Predictions for LOCA Analysis,” C183.pdf in Proc. of PHYSOR–2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, September 10–14, 2006, Vancouver, British Columbia, Canada.

I. C. Gauld, S. M. Bowman and B. D. Murphy, "Application of ORIGEN to Spent Fuel Safeguards and Non-Proliferation," in Proc.of INMM 47th Annual Meeting, July 16–20, 2006, Nashville, Tennessee.

Zhaopeng Zhong, Thomas J. Downar, Mark D. DeHart, and Mark L. Williams, “Parallelization of the SCALE Continuous-Energy Resonance Processing Module GEMINEWTRN,” Trans. Am. Nucl. Soc., 94, 473–475 (2006).

Germina Ilas and Ian C. Gauld, “Analysis of Decay Heat Measurements for BWR Fuel Assemblies,” Trans. Am. Nucl. Soc., 94, 385–387 (2006).

Zhaopeng Zhong and Mark D. DeHart, “Coarse–Mesh Finite–Difference Acceleration in the NEWT Generalized-Geometry Lattice Physics Package,” Trans. Am. Nucl. Soc., 94, 471–472 (2006).

D. E. Peplow and J. C. Wagner, "Automated Variance Reduction for SCALE Shielding Calculations," in Proc. of ANS 14th Biennial Topical Meeting of the Radiation Protection and Shielding Division, pp. 556-558, Carlsbad, New Mexico, April 2-6, 2006.

R. D. Busch and S. M. Bowman, KENO V.a Primer: A Primer for Criticality Calculations with SCALE/KENO V.a Using GeeWiz, ORNL/TM-2005/135, UT-Battelle, LLC, Oak Ridge National Laboratory, December 2005. [Export Controlled Document published on CD-ROM and distributed by RSICC.]

S. Goluoglu and M. L. Williams, "Modeling Doubly Heterogeneous Systems in SCALE," Trans. Am. Nucl. Soc. 93, 963-965 (2005).

D. F. Hollenbach and P. B. Fox, "Benchmark Analysis of the SCALE 5 Versions of the KENO-VI and CENTRM Codes," dfz-2.pdf in Proc. of 2005 NCSD Topical Meeting – Integrating Criticality Safety into the Resurgence of Nuclear Power, September 19–22, 2005, Knoxville, Tennessee, on CD-ROM, American Nuclear Society, LaGrange Park, Illinois (2005).

D. F. Hollenbach and M. E. Dunn, "Status and Preliminary Testing of Continuous-Energy KENO V.a and KENO-VI Results," dfz-1.pdf in Proc. of 2005 NCSD Topical Meeting – Integrating Criticality Safety into the Resurgence of Nuclear Power, September 19–22, 2005, Knoxville, Tennessee, on CD-ROM, American Nuclear Society, LaGrange Park, Illinois (2005).

D. E. Mueller and B. T. Rearden, "Sensitivity Coefficient Generation for a Burnup Credit Cask Model using TSUNAMI-3D," reardenb-2.pdf in Proc. of 2005 NCSD Topical Meeting, September 19-22, 2005, Knoxville, Tennessee.

S. Goluoglu and C. M. Hopper, "Application of Validation Methodologies for a Generic Validation Problem," sedat-2.pdf in Proc. of 2005 NCSD Topical Meeting – Integrating Criticality Safety into the Resurgence of Nuclear Power, September 19–22, 2005, Knoxville, Tennessee, on CD-ROM, American Nuclear Society, LaGrange Park, Illinois (2005).

S. M. Bowman, B. T. Rearden, and J. E. Horwedel, “ Complete User Visualization Interface for KENO,” stevebowman-1.pdf in Proc. of 2005 NCSD Topical Meeting – Integrating Criticality Safety into the Resurgence of Nuclear Power, September 19–22, 2005, Knoxville, Tennessee, on CD-ROM, American Nuclear Society, LaGrange Park, Illinois (2005).

I. C. Gauld and D. E. Mueller, Evaluation of Cross-Section Sensitivities in Computing Burnup Credit Fission Product Concentrations, ORNL/TM-2005/48, Oak Ridge National Laboratory, Oak Ridge, Tennessee, August 2005.

B. T. Rearden, W. J. Anderson, and G. A. Harms, "Use of Sensitivity and Uncertainty Analysis in the Design of Reactor Physics and Criticality Benchmark Experiments for Advanced Nuclear Fuel," Nucl. Technol. 151, 133-158 ( August 2005).

Return to SCALE Home