Oak Ridge National Laboratory

Reactor Analysis


Quick Links 2004 2005 2006  2007 2008 2009
 
Author(s) / Report Title / Publication Number / Date
2009
Matthew A. Jessee, Mark L. Williams, and Mark D. DeHart, “Development of Generalized Perturbation Theory Capability within the SCALE Code Package,” 201120.pdf in Proc. of International Conference on Mathematics, Computational Methods, and Reactor Physics (M&C 2009), May 3–7, 2009, Saratoga Springs, New York.
Mark L. Williams and Germina Ilas, “ENDF/B-VII Nuclear Data Libraries for SCALE 6,” usr-xmw-1-paper.pdf, Advances in Nuclear Fuel Management IV (ANFM 2009),Hilton Head Island, South Carolina, USA, April 12–15, 2009, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2009).
Germina Ilas, R. T. Primm, III, and Jess C. Gehin, “Designing a New Fuel for HFIR—Performance Parameters for LEU Core Configurations,” usr-gilas-1-paper.pdf, Advances in Nuclear Fuel Management IV (ANFM 2009), Hilton Head Island, South Carolina, USA, April 12–15, 2009, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2009).

Ronald J. Ellis, “Reactor Physics Assessment of the Inclusion of Unseparated Neptunium in MOX Reactor Fuel,” usr-ron55-1-paper.pdf, Advances in Nuclear Fuel Management IV (ANFM 2009), Hilton Head Island, South Carolina, USA, April 12–15, 2009, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2009).
2008
C. F. Weber and V. J. Jodoin, “Characterization of Fallout from an Urban Nuclear Detonation,”4th Joint DOD/DOE Nuclear Survivability Weapon Effects Modeling and Simulation Workshop, December 16–17, 2008, Huntsville, Alabama.  
D. A. Hooper and V. J. Jodoin, “Modification of the Defense Land Fallout Interpretive Code (DELFIC) for Urban Detonations,” 4th Joint DOD/DOE Nuclear Survivability Weapon Effects Modeling and Simulation Workshop, December 16–17, 2008, Huntsville, Alabama.  
M. L. Williams and B. T. Rearden, “SCALE-6 Sensitivity/Uncertainty Methods and Covariance Data,” Nuclear Data Sheets, Vol. 109, Issue 12, 2796–2800 (December 2008), Special Issue on Workshop on Neutron Cross Section Covariances, June 24-28, 2008, Port Jefferson, USA. 
R. C. Little, T. Kawano, G. D. Hale, M. T. Pigni, M. Herman, P. Oblozinsky, M. L. Williams, M. E. Dunn, G. Arbanas, D. Wiarda, R. D. McKnight, J. N. McKamy, and J. R. Felty, “Low-fidelity Covariance Project,” Nuclear Data Sheets, Vol. 109, Issue 12, 2828–2833 (December 2008), Special Issue on Workshop on Neutron Cross Section Covariances, June 24-28, 2008, Port Jefferson, USA. 
Mark D. DeHart and Megan L. Pritchard, “Validation of SCALE and the TRITON Depletion Sequences for Gas Reactor Analysis,” Trans. Am. Nuc. Soc., 99, 683–685 (November 2008). 
Mark. D. DeHart, Ian C. Gauld, and Kenya Suyama, “ Issues in Three-Dimensional Depletion Analysis of Measured Data Near the End of a Fuel Rod,” Trans. Am. Nuc. Soc., 99, 663–666. (November 2008). 
Yaqi Wang, Jean C. Ragusa, Mark D. DeHart, and Kevin T. Clarno, “Progress in the Integration of the 2D DG-FEM SN Transport Solver Xuthus into SCALE,” Trans. Am. Nuc. Soc., 99, 750–752 (November 2008). 
Germina Ilas and Ian C. Gauld, “Analysis of isotopic assay data from the MALIBU program,” FP215.pdf in Proc. of PHYSOR’08 International Conference on the Physics of Reactors “Nuclear Power: A Sustainable Resource,” September 14–19, 2008, Interlaken, Switzerland.  
Mark D. DeHart, Ian C. Gauld, and Kenya Suyama, “Three-dimensional depletion analysis of the axial end of a Takahama fuel rod,” FP243.pdf in Proc. of PHYSOR’08 International Conference on the Physics of Reactors “Nuclear Power: A Sustainable Resource,” September 14–19, 2008, Interlaken, Switzerland. 
Germina Ilas, Jess C. Gehin, and R. T. Primm, III, “New cross section processing methodology for HFIR core analysis,” FP502.pdf in Proc. of PHYSOR’08 International Conference on the Physics of Reactors “Nuclear Power: A Sustainable Resource,” September 14–19, 2008, Interlaken, Switzerland. 
M. L. Williams, J. C. Gehin, and Won Sik Yang, “Combining MC2-2 and SCALE cross section methods to process nuclear data for GNEP,” FP589.pdf in Proc. of PHYSOR’08 International Conference on the Physics of Reactors “Nuclear Power: A Sustainable Resource,” September 14–19, 2008, Interlaken, Switzerland. 
Ronald J. Ellis, Jess C. Gehin, Joel L. McDuffee, and Randy W. Hobbs, “Analysis of a fast spectrum irradiation facility in the high flux isotope reactor,” FP533.pdf in Proc. of PHYSOR’08 International Conference on the Physics of Reactors “Nuclear Power: A Sustainable Resource,” September 14–19, 2008, Interlaken, Switzerland.
Sergiy A. Vilkomir, W. Thomas Swain, Jesse H. Poore, and Kevin T. Clarno, “Modeling Input for Space Testing Scientific Computational Software:  A Case Study,” pp. 291–300 in Computational Sciences-ICCS 2008, 8th International Conference, Proceedings, Part III, June 23–25, 2008, Krakow, Poland.
Joel L. McDuffee, Jess C. Gehin, Ronald J. Ellis, Randy W. Hobbs, and Trent Primm, “Proposed Fuel Pin Irradiation Facilities for the High Flux Isotope Reactor,” paper 8424 pp. 2645–2651 in Proc. of ICAPP ’08, June 8–12, 2008, Anaheim, California.

J. C. Gehin, R. E. Ellis, J. L. McDuffee, R. W. Hobbs, and L. L. Snead, “Development of Fast Spectrum Irradiation Facility for Fuels Development in the High Flux Isotope Reactor,” 03-Gehin-ORNL HFIR Fast Neutron Irradiation Capability-ARWIF2008.pdf in Proc. of Workshop on Advanced Reactors with Innovative Fuels (ARWIF 2008), February 20–22, 2008, Tsuruga/Fukui, Japan.

T. E. Greifenkamp, K. T. Clarno, and J. C. Gehin, “Effect of Fuel Temperature Profile on Eigenvalue Calculations,” 2008 American Nuclear Society National Student Conference, February 28–March 1, 2008, College Station, Texas.

G. Ilas and I. C. Gauld, “SCALE analysis of CLAB decay heat measurements for LWR spent fuel assemblies,”Annals of Nuclear Energy, Vol. 35, No. 1, p. 37-48 (January 2008).

2007
Ronald J. Ellis, “ Prospects of Using Reprocessed Uranium in CANDU Reactors, in the US GNEP Program,” The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, November 11–15, 2007, Washington, D.C. Trans. Am. Nucl. Soc .97, 107–108 (2007).
Mark D. DeHart, “High-Fidelity Lattice Physics Capabilities of the SCALE Code System Using TRITON,” The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, November 11–15, 2007, Washington, D.C. Trans. Am. Nucl. Soc. 97, 598–600 (2007).
J. P. Renier, L. D. Trowbridge, and G. D. Del Cul, “Reuse in LWRs of Uranium Recovered from Spent Fuel: Neutronic Evaluation of Multiple Cycles of Re-enrichment and Reactor Irradiation,” The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, November 11–15, 2007, Washington, D.C. Trans. Am. Nucl. Soc. 97, 94–95 (2007).
Steven Hamilton, Cassiano de Oliveira, Kevin T. Clarno, “Error Control in a Time-Dependent Slice-Balance Method,” The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, November 11–15, 2007, Washington, D.C. Trans. Am. Nucl. Soc. 97, 533–600 (2007).
L. D. Trowbridge, J. P. Reiner, and G. D. Del Cul, “Evaluation of Reuse of Reprocessed Uranium in the Context of the U. S. Global Nuclear Energy Partnership Program,” The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, November 11–15, 2007, Washington, D.C. Trans. Am. Nucl. Soc. 97, 105–106 (2007).
Seth R. Johnson and Kevin T. Clarno, “Implementation of Transport Synthetic Acceleration in NEWTRNX,” The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, November 11–15, 2007, Washington, D.C. Trans. Am. Nucl. Soc. 97, 491–493 (2007).
Germina Ilas, Brian D. Murphy, and Ian C. Gauld, “Overview of ORIGEN-ARP and its Applications to VVER RBMK,” The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, November 11–15, 2007, Washington, D.C. Trans. Am. Nucl. Soc. 97, 601–603 (2007).
Kevin T. Clarno, “Implementation of Generalized Coarse-Mesh Rebalance of NEWTRNX for Acceleration of Parallel Block-Jacobi Transport,” The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, November 11–15, 2007, Washington, D.C. Trans. Am. Nucl. Soc. 97, 498–500 (2007).
G. D. Del Cul, L. D. Trowbridge, J. P. Renier, R. J. Ellis, K. A. Williams, and E. D. Collins, “Possible Recycle of Most Components from LWR Spent Fuel Including Uranium, Cladding and Transuranium Elements,” The American Nuclear Society and the European Nuclear Society 2007 International Conference on Making the Renaissance Real, November 11–15, 2007, Washington, D.C. Trans. Am. Nucl. Soc. 97, 77-78 (2007).
M. L. Williams, B. L. Broadhead, M. E. Dunn, and B. T. Rearden, “Approximate Techniques for Representing Nuclear Data Uncertainties,” p. 744-752 in Proc. of the Eighth International Topical Meeting on Nuclear Applications and Utilization of Accelerator (ACCAPP '07), July 30–August 2, 2007, Pocatello, Idaho.
Seth R. Johnson and Kevin T. Clarno, “Comparison of SCALE and MCNP Results for Computational Pebble Bed Benchmarks,” American Nuclear Society 2007 Annual Meeting “It’s All About the People: The Future of Nuclear,” June 24–28, 2007, Boston, Massachusetts. Trans. Am. Nucl. Soc , 96, p.420–422 (2007).
Ronald J. Ellis, Jess C. Gehin, Germina Ilas, and R. T. Primm, III, “Neutronics Feasibility Study for Conversion of the High Flux Isotope Reactor with LEU U-7Mo Dispersion Fuel,” American Nuclear Society 2007 Annual Meeting “It’s All About the People: The Future of Nuclear,” June 24–28, 2007, Boston, Massachusetts. Trans. Am. Nucl. Soc , 96, p.620–622 (2007).
Germina Ilas, Brian D. Murphy, and Ian C. Gauld, “VVER and RBMK Cross Section Libraries for ORIGEN-ARP,” p. 413–417 in Proceedings of the 8th International Conference on Nuclear Criticality Safety (ICNC 2007), Vol. II, May 28–June 1, 2007, St. Petersburg, Russia.
Stephen M. Bowman, Mark D. DeHart, Michael E. Dunn, Sedat Goluoglu, James E. Horwedel, Lester M. Petrie, Jr., Bradley T. Rearden, and Mark L. Williams, “New Criticality Safety Analysis Capabilities in SCALE 5.1,” p. 403–407 in Proceedings of the 8th International Conference on Nuclear Criticality Safety (ICNC 2007), Vol. I, May 28–June 1, 2007, St. Petersburg, Russia.

M. D. DeHart and S. M. Bowman, “Improved radiochemical assay analyses using TRITON depletion sequences in SCALE,” Proc. of International Atomic Energy Agency Technical Meeting “Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition,” August 29–September 2, 2005, London, United Kingdom.  IAEA-TECDOC-CD-1547, Session 2, pg. 99–108 (May 2007).

B. D. Ganapol, K. T. Clarno, and Seth Johnson, “An Embedded Semi-Analytical Benchmark via Iterative Interpolation for Neutron Transport Methods Verification,” mcsna01371full.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).

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, 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).
Z. Zhong, T. J. Downar, Y. Xu, M. D. DeHart, and K. T. Clarno, “Implementation of Two-Level Coarse-Mesh Finitie-Difference Acceleration in an Arbitrary Geometry Two-Dimensional Discrete-Ordinates Transport Method,” submitted for publication in Nucl. Sci. Eng.
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.
2006
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).
J. J. Klingensmith, Y. Y. Azmy, and I. C. Gauld, “Implementation and Verification of AMALGAMATE, an Interfacing Tool for TORTSQ and ORIGEN-S,” Trans. Am. Nucl. Soc., 95, 312–314 (2006).
E. D. Collins and J. P. Renier, “Comparative Evaluation of TRU Actinide Transmutation in Fast and Thermal Burner Reactors,” Trans. Am. Nucl. Soc., 95, 224–226 (2006).

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

R. T. Primm III, R .J . Ellis, J .C . Gehin, K .T . Clarno, K .A . Williams, and D .L . Moses, Design Study for a Low-Enriched Uranium Core for the High Flux Isotope Reactor, Annual Report for FY 2006, ORNL/TM-2006/136, UT-Battelle, LLC, Oak Ridge National Laboratory, October 2006.

J. Tholammakkil, Farzad Rahnema, Germina Ilas, Rudi Stamm’ler, Vladimir Khotylev and Dumitru Serghiuta, “Impact of Lattice Geometry Distortion due to Ageing on Selected Physics Parameters of a CANDU Reactor,” C143.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.

M. C. Brady Raap, I. C. Gauld, J. K. Dickens, and W. B. Wilson, “Revisions to the Decay Heat Standard: ANSI/ANS 5.1,” C125.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.

Zhaopeng Zhong, Thomas J. Downar, Mark D. DeHart, and Kevin T. Clarno, “Coarse Mesh Finite Difference Acceleration in the Two-Dimensional Discrete Ordinates Transport Calculation,” A034.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.

Zhaopeng Zhong, Thomas J. Downar, Mark D. DeHart, and Mark L. Williams, “Parallelization in SCALE Continuous-Energy Resonance Module GEMINEWTRN and Transport Module NEWT,” A051.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 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 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.

Kevin T. Clarno and Jess C. Gehin, "Physics Analysis of the LS-VHTR: Salt Coolant and Fuel Block Design," D045.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.

Kevin Clarno, Valmor de Almeida, Ed d’Azevedo, Cassiano de Oliveira, and Steven Hamilton, “GNES-R: Global Nuclear Energy Simulator for Reactors Task 1: High-Fidelity Neutron Transport,” D025.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.

R. J. Ellis, J. C. Gehin, and R. T. Primm, III, “Cross Section Generation and Physics Modeling in a Feasibility Study of the Conversion of the High Flux Isotope Reactor Core to use Low-Enriched Uranium Fuel,” B021.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.

R. T. Primm, III, R. J. Ellis, J. C. Gehin, D. L. Moses, J. L. Binder, and N. Xoubi, “Assumptions and Criteria for Performing a Feasibility Study of the Conversion of the High Flux Isotope Reactor Core to Use Low-Enriched Uranium Fuel,” D135.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 C. Gauld, Stephen M. Bowman, Brian D. Murphy, and P. Schwalbach, “Applications of ORIGEN to Spent Fuel Safeguards and Non-Proliferation,” 431_gauldian.pdf in Proc. of INMM 47th Annual Meeting, July 16–20, 2006, Nashville, Tennessee.

Germina Ilas and Ian C. Gauld, “Analysis of Decay Heat Measurements for BWR Fuel Assemblies,” 2006 ANS Annual Meeting “ A Brilliant Future: Nexus of Public Support in Nuclear Technology,” June 4–9, 2006, Reno, Nevada. 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,” 2006 ANS Annual Meeting, “A Brilliant Future: Nexus of Public Support in Nuclear Technology,” June 4–8, 2006, Reno, Nevada. Trans. Am. Nucl. Soc., 94, 471–472 (2006).

Zhaopeng Zhong, Thomas J. Downar, Mark D. DeHart, and Mark L. Williams, “Parallelization of the SCALE Continuous-Energy Resonance Processing Module GEMINEWTRN,” 2006 ANS Annual Meeting, “A Brilliant Future: Nexus of Public Support in Nuclear Technology,” June 4–8, 2006, Reno, Nevada. Trans. Am. Nucl. Soc., 94, 473–475 (2006).

Felix C. Difilippo, “Reactivity Biases in the Simulation of the Random Dispersal of Fuel: The Case of VHTR Fuel Compact,” 2006 ANS Annual Meeting “A Brilliant Future: Nexus of Public Support in Nuclear Technology,” June 4–8, 2006, Reno, Nevada. Trans. Am. Nucl. Soc., 94, 556–557 (2006).

B. D. Murphy, “Benchmarking of SCALE 5 Nuclide Predictions for VVER-440 Spent-Fuel Samples for the Novovoronezh Reactor,” in Proc. of the Post Irradiation Experiments to Validate Fuel Depletion Calculation Methodologies, May 11–12, 2006, Rez, Czech Republic.

R. T. Primm, III, R. J. Ellis, and J. C. Gehin, “Preliminary Report – Design Study for a Low Enriched Uranium (LEU) Core for the High Flux Isotope Reactor (HFIR)”, ORNL/TM-2006/80, April 20, 2006.

R. T. Primm III, R. J. Ellis, J. C. Gehin, D. L. Moses, and J. L. Binder, Assumptions and Criteria for Performing a Feasibility Study of the Conversion of the High Flux Isotope Reactor Core to use Low-Enriched Uranium Fuel, ORNL/TM-2005/269, UT-Battelle, LLC, Oak Ridge National Laboratory, February 2006.
2005

D. T. Ingersoll, K. T. Clarno, C. W. Forsberg, J. C. Gehin, R. W. Christiansen, C. B. Davis, G. L. Hawkes, J. W. Sterbentz, T. K. Kim, T. A. Taiwo, and W. S. Yang, Status of Physics and Safety Analysis for the Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR), ORNL/TM-2005/218, UT-Battelle, LLC, Oak Ridge National Laboratory, December 2005.

R. T. Primm III, R. J. Ellis, J. C. Gehin, D. L. Moses, J. L. Binder, Assumptions and Criteria for Performing a Feasibility Study of the Conversion of the High Flux Isotope Reactor Core to Use Low-Enriched Uranium Fuel, ORNL/TM-2005/269, UT-Battelle, LLC, Oak Ridge National Laboratory, November 2005.
Kevin. T. Clarno, Charles W. Forsberg, and Jess C. Gehin, “Physics Analysis of Coolant Voiding in the Advanced High-Temperature Reactor (AHTR),” 2005 ANS Winter Meeting,“Talk About Nuclear Differently: A Good Story Untold,” November 13-17, 2005, Washington, D. C. Trans. Am. Nucl. Soc. 93, 977–980 (2005).
K. T. Clarno, M. L. Williams, J. C. Gehin, C. Cotton, D. Lee, and T. Downar, "Code-to-Code Benchmark of Coolant Void Reactivity (CVR) in the ACR-700 Reactor," 2005 ANS Winter Meeting, "Talk About Nuclear Differently: A Good Story Untold," November 13-17, 2005, Washington, D. C. Trans. Am. Nucl. Soc. 93, 372-375 (2005).

R. T. Primm, III, D. L. Moses, J. C. Gehin, R. J. Ellis, and J. L. Binder, “Overview of High Flux Isotope Reactor Design Basis Relevant to Possible Conversion to Low Enriched Uranium,” in Proc. of 2005 RERTR International Meeting on Reduced Enrichment for Research and Test Reactors, November 6–11, 2005, Boston, Massachusetts.

D. F. Williams, L. M. Toth, K. T. Clarno, and C. W. Forsberg, “ Assessment of Properties of Candidate Liquid Salt Coolants for the Advanced High-Temperature Reactor (AHTR),” ORNL/GEN4/LTR-05-001.

M. Biro, J. W. Cletcher, D. A. Copinger, R. J. Ellis, G. F. Flanagan, M. A. Linn, M. D. Muhlheim, L. D. Proctor, and D. L. Williams, Jr., Prototype Risk Evaluation Assessment Model for the ACR-700 Advanced CANDU Reactor, NUREG/CR-XXXX (ORNL/TM-2005/130), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory (submitted to NRC).

F. Difilippo and J. Renier , “Effects of the Laurent and Taylor Expansions on the Calculations of the Thermal Neutrons Inelastic Scattering Cross Sections for Crystalline Moderators,” Ann. Nuc. Energy, 32(12), pp. 1323-1336 (August 2005).

F. C. Difilippo and I. C. Gauld, ORIGEN-ARP Cross-Section Libraries for Analysis of Spent Nuclear Fuel from South Korean Reactors, ORNL/TM-2005/95, UT-Battelle, LLC, Oak Ridge National Laboratory, August 2005.

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

R. J. Belles, B. B. Bevard, J. J. Carbajo, and J. C. Gehin, ORNL Fissile Material Disposition Program: FY05 Programmatic, Technical, and Financial Report on the State of the VVER-1000 Project, ORNL/MD/LTR-286, UT-Battelle, LLC, Oak Ridge National Laboratory, August 2005.

F. Difilippo and J. Renier, “Effects of the Laurent and Taylor Expansions on the Calculations of the Thermal Neutrons Inelastic Scattering Cross Sections for Crystalline Moderators,” Ann. Nuc. Energy,32 (12), pp 1323-1336 (August 2005).

I. C. Gauld and D. E. Mueller, Status and Recommendations for Acquisition of Fission Product Radiochemical Assay Data, ORNL/TM-2005/47, UT-Battelle, LLC, Oak Ridge National Laboratory, June 2005.

Z. Zhong, T. Downar, and M. DeHart, Implementation of a Two-Level Coarse-Mesh Finite-Difference Accelerator in the NEWT Transport Code, ORNL/TM-2004/162, UT-Battelle, LLC, Oak Ridge National Laboratory, June 2005.

F. C. Difilippo , and J. P. Renier, “Double Differential Neutron Scattering Cross Sections for Ultra High Temperature Materials,” 2005 ANS Annual Meeting, “The Next 50 Years: Creating Opportunities,” June 5–9, 2005, San Diego, California. Trans. Am. Nucl. Soc., 92, 558–560 (2005).

Z. Zhong, T. J. Downar, M. D. DeHart, and M. L. Williams, “Continuous-Energy Multidimensional SN Transport for Problem-Dependent Resonance Self-Shielding Calculations,” 2005 ANS Annual Meeting, “The Next 50 Years: Creating Opportunities,” June 5–9, 2005, San Diego, California. Trans. Am. Nucl. Soc., 92, 754–757 (2005).

J. Pounders, F. Rahnema and G. Ilas, “CANDU core calculations with Monte Carlo based homogenized cross sections,” 2005 ANS Annual Meeting, “The Next 50 Years: Creating Opportunities,” June 5–9, 2005, San Diego, California. Trans. Am. Nucl. Soc., 92, 525-527 (June 2005).

J. J. Klingensmith and I. Gauld, “ORIGEN-S Gamma Decay Spectra Characterization and Benchmarking,” 2005 ANS Annual Meeting, “The Next 50 Years: Creating Opportunities,” June 5–9, 2005, San Diego, California. Trans. Am. Nucl. Soc., 92, 33-34 (June 2005).

G. Ilas and F. Rahnema, “Effect of fuel particles distribution model on PBR cell parameters,” 2005 ANS Annual Meeting, “The Next 50 Years: Creating Opportunities,” June 5–9, 2005, San Diego, California. Trans. Am. Nucl. Soc., 92, 654-656 (June 2005).

F. C. Difilippo and J. P. Renier , “Double Differential Neutron Scattering Cross Sections for Ultra High Temperature Materials,” 2005 ANS Annual Meeting, “The Next 50 Years: Creating Opportunities,” June 5–9, 2005, San Diego, California. Trans. Am. Nucl. Soc., 92, 558-560 (June 2005).

M. D. DeHart , J. Sacchari and D. Diamond, “Assessment of TRITON and PARCS for Full-Core MOX Fuel Calculations,” 2005 ANS Annual Meeting, “The Next 50 Years: Creating Opportunities,” June 5–9, 2005, San Diego, California. Trans. Am. Nucl. Soc., 92, 763-766 (June 2005).

Z. Zhong, T. J. Downar, M. D. DeHart, and M. L. Williams, “Continuous-Energy Multidimensional SN Transport for Problem-Dependent Resonance Self-Shielding Calculations,” 2005 ANS Annual Meeting, “The Next 50 Years: Creating Opportunities,” June 5–9, 2005, San Diego, California. Trans. Am. Nucl. Soc., 92, 754-757 (June 2005).

M. Biro, J. W. Cletcher, D. A. Copinger, R. J. Ellis, G. F. Flanagan, M. A. Linn, M. D. Muhlheim, L. D. Proctor, and D. L. Williams, Jr., Prototype Risk Evaluation Model for the ACR-700 Advanced CANDU Reactor, NUREG/CR-XXXX, (ORNL/TM-2005/130), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, May 2005 (DRAFT).

B. D. Murphy, Calculating Fork Detector Response from Spent-Fuel Inventories Using Monte-Carlo Techniques, ORNL/TM-2004/310, UT-Battelle, LLC, Oak Ridge National Laboratory, May 2005.

B. D. Murphy and P. De Baere, “Monte Carlo Modeling of a Fork Detector System,” in Proc. of the 27th ESARDA Annual Meeting, May 10–12, 2005, London, England.

C. W. Forsberg and K. T. Clarno, “The Advanced High-Temperature Reactor (AHTR): Flux Distribution and Dosimetry,” Twelfth International Symposium on Reactor Dosimetry, May 8–13, 2005, Gatlinburg, TN, to be published in J. of ASTM International, ASTM, West Conshohocken, PA (in press).

E. D. Gugiu, R. J. Ellis, and C. S. Roth, “The Applications of Monte Carlo Codes to Romanian TRIGA and CANDU Reactors,” usr-daniela-1-paper.pdf in Proc. of Monte Carlo 2005 Topical Meeting, The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, April 17–21, 2005, Chattanooga, Tennessee; on CD-ROM, American Nuclear Society, LaGrange Park, Illinois (2005).

S. M. Bowman, M. D. DeHart, and L. M. Petrie, “ Integrated KENO Monte Carlo Transport for 3-D Depletion with SCALE,” usr-stevebowman-1-paper.pdf in Proc. of The Monte Carlo 2005 Topical Meeting, The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, April 17–21, 2005, Chattanooga, Tennessee; on CD-ROM, American Nuclear Society, LaGrange Park, Illinois (2005).

K. T. Clarno and M. L. Adams, “Capturing the Effects of Unlike Neighbors in Single Assembly Calculations,” Nuc. Sci. & Eng.,149(2), pp 182-196 (February 2005).

D. T. Ingersoll, E. J. Parma, C. W. Forsberg, and J. P. Renier, “Core Physics Characteristics and Issues for the Advanced High-Temperature Reactor (AHTR) Concept,” Workshop on Advanced Reactors with Innovative Fuels (ARWIF-2004), February 16–18, 2005, Oak Ridge, TN, Nuclear Science Committee, OECD Nuclear Energy Agency, Paris, France (in press).

E. D. Gugiu, R. J. Ellis, I. Dumitrache, and M. Constantin, “An Analysis of the Nuclear Data Libraries’ Impact on the Criticality Computations Performed Using Monte Carlo,” in AIP Conference Proceedings, 769, 1423 (2005); International Conference on Nuclear Data for Science and Technology, September 26–October 1, 2004, Santa Fe, New Mexico.

2004
K. Hesketh, G. Schlosser, D. F. Porsch, T. Wolf, O. Köberl, B. Lance, R. Chawla, J. C. Gehin, R. J. Ellis, S. Uchikawa, O. Sato, T. Okubo, H. Mineo, T. Yamamoto, Y. Sagayama, E. Sartori “Plutonium Management in the Medium Term,” Nuc. Tech., 148 (3), pp 244-258 (December 2004).
Y. Azmy, J. C. Gehin, R. Orsi, “ DORT Solutions to the Two-Dimensional C5G7MOX Benchmark Problem,” Progress in Nuclear Energy,45 (2-4), pp. 215-231 (2004).
F. C. Difilippo, “Analysis of VHTR's with the SCALE System,” Trans. Am. Nuc. Soc.,91, 763‑765 (November 2004).
I. C. Gauld, “Automated Depletion Analysis of PBMR Fuel Using SCALE,” Trans. Am. Nuc. Soc., 91 , 673–674 (November 2004).
B. D. Murphy and I. C. Gauld, “Spent-Fuel Decay Heat Investigations for BWR Assemblies Using Both One- and Two-Dimensional Model Simulations,” Trans. Am. Nuc. Soc.,91, 670–672 (November 2004).
M. D. DeHart and L. M. Petrie, “ Integrated KENO V.a Monte Carlo Transport for Multidimensional Depletion Within Scale,”Trans. Am. Nucl. Soc., 91, 667–669 (November 2004).
J. C. Gehin, J. J. Carbajo, and R. J. Ellis, Issues in the Use of Weapons-Grad MOX Fuel in VVER-1000 Nuclear Reactors: Comparison of UO 2and MOX Fuels, ORNL/TM-2004/223, UT-Battelle, LLC, Oak Ridge National Laboratory, October 2004.
E. D. Collins and J. P. Renier, “Evaluation of Actinide Partitioning and Transmutation in Light-Water Reactors,” in Proc. of Atalante 2004 Advances for Future Nuclear Cycles, June 21–24, 2004, Nimes, France.
D. T. Ingersoll, C. W. Forsberg, L. J. Ott, D. F. Williams, J. P. Renier, D. F. Wilson, S. J. Ball, R. L. Reid, W. R. Corwin, G. D. Decul, P. F. Peterson, H. Zhao, P. S. Pickard, E. J. Parma, and M. Vernon, Status of Preconceptual Design of the Advanced High Temperature Reactor (AHTR), ORNL/TM-2004/104, UT-Battelle, LLC, Oak Ridge National Laboratory, May 2004.
I. C. Gauld and B. D. Murphy, Updates to the ORIGEN-S Data Libraries Using ENDF/B-VI, FENDL-20, and EAF-99 Data, ORNL/TM-2003/118, May 2004.
B. D. Murphy, ORIGEN-ARP Cross-Section Libraries for Magnox, Advanced Gas-Cooled, and VVER Reactor Designs, ORNL/TM-2003/263, UT-Battelle, LLC, Oak Ridge National Laboratory, February 2004.


Return Publications - Home Page     Return to the ORNL NSTD Home Page

 
ORNL       NSTD       NSADS       Index       Search       Comments       Disclaimers