Oak Ridge National Laboratory

Nuclear Engineering Applications Section
1991

  Author(s) / Report Title / Publication Number / Date
C. F. Weber,  Calculation of Absorbed Doses to Water Pools in Severe Accident Sequences, NUREG/CR-5808 (ORNL/TM-11970), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1991.
R. M. Westfall, K. S. Joy, and C. M. Horak,  The 1990 Annual Criticality Review Committee Appraisal, ORNL/CF-91/53, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1991.
M. L. Williams, C. Aboughantous, M. Asagari, J. E. White, R. Q. Wright, and F. B. K. Kam, ENDF/B-V, Revised ENDF/B-V, and ENDF/B-VI Iron Evaluations, NUREG/CR-5648 ( ORNL/TM-11686), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1991.
M. L. Williams, C. Aboughantous, M. Asagari, J. E. White, R. Q. Wright, and F. B. K. Kamr, "Transport Calculations of Neutron Transmission Through Steel Using ENDF/B-V and ENDF/B-VI Iron Evaluations," Ann. Nucl. Energy, 18(10), 549-565 (1991).
G. D. Kerr, J. S. Tang, and R. L. Childs, "A New Radiation Dosimetry for the 1958 Criticality Accident at the Oak Ridge Y-12 Plant,"  Health Phys., 60 (1991).
W. A. Rhoades and R. L. Childs, "The Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code," Nucl. Sci. Eng., 107, 397-398 (1991).
G. A. Aramayo, C. M. Hopper, J. R. Kirkpatrick, D. M. McGinty, J. T. Muecke, and J. C. Walls,  Safety Analysis Report for Packaging: The ORNL HFIR Unirradiated Fuel Element Shipping Container, Vol. 1, ORNL/TM-11656/V1, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1991.
G. A. Aramayo, C. M. Hopper, J. R. Kirkpatrick, D. M. McGinty, J. T. Muecke, and J. C. Walls, Safety Analysis Report for Packaging: The ORNL HFIR Unirradiated Fuel Element Shipping Container, Vol. 2, ORNL/TM-11656/V2, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1991.
M. C. Brady, R. Q. Wright, and T. R. England,  Actinide Nuclear Data for Reactor Physics Calculations, ORNL/CSD/TM-266, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1991.
K. F. Eckerman, J. C. Ryman, J. S. Tang, L. R. Williams, and J. V. Pace, "Improved Dose Rate Factors for Exposure to Photons from Contaminated Soil,"  Health Phys., 60, S83, (1991).
R. L. Childs, L. M. Petrie, and N. F. Landers, A User's Guide for the Starter Computer Program, ORNL/TM-11872, Martin Marietta Energy Systems, Oak Ridge National Laboratory, December 1991.
O. W. Hermann, M. C. Brady, and C. V. Parks, "Validation of Spent Fuel Isotopics Predicted by the SCALE-4 Depletion Sequence," 1991 Winter Meeting American Nuclear Society, November 10-14, 1991, San Francisco, California.  Trans. Am. Nucl. Soc.,  64, 147-149 (1991).
D. F. Hollenbach, W. Newmeyer, B. Basoglu, H. L. Dodds, N. F. Landers, and L. M. Petrie,  "Vectorization of the KENO V.a Criticality Safety Code," 1991 Winter Meeting American Nuclear Society, November 10-14, 1991, San Francisco, California.  Trans. Am. Nucl. Soc., 64, 348-349 (1991).
C. M. Hopper,  "ANSI/ANS-8.7-1982(R88) Guide for Nuclear Criticality Safety in the Storage of Fissile Materials," 1991 Winter Meeting American Nuclear Society, November 10-14, 1991, San Francisco, California.  Trans. Am. Nucl. Soc., 64, 330 (1991).
W. D. Newmeyer, B. Basoglu, D. F. Hollenbach, and H. L. Dodds, "Analysis of a Hypothetical Criticality Accident Involving Dry Highly Enriched Uranium Powder," 1991 Winter Meeting American Nuclear Society, November 10-14, 1991, San Francisco, California.  Trans. Am. Nucl. Soc., 64, 344 (1991).
R. Q. Wright and J. E. White, "Fast Reactor Data Testing of ENDF/B-VI at ORNL," 1991 Winter Meeting American Nuclear Society, November 10-14, 1991, San Francisco, California. Trans. Am. Nucl. Soc., 64, 566-68 (1991).
M. L. Williams, R. E. MacFarlane, M. Milgram, R. Q. Wright, and A. C. Kahler, "Initial Data Testing of ENDF/B-VI for Thermal Reactor Benchmark Analysis," 1991 Winter Meeting American Nuclear Society, November 10-14, 1991, San Francisco, California. Trans. Am. Nucl. Soc., 64, 561-562 (1991).
J. C. Ryman, K. F. Eckerman, J. S. Tang, L. R. Williams, and J. V. Pace, "Organ Doses Due to Exposure to External Radiation Fields," Proc. of 3rd Conf. on Radiation Protection and Dosimetry, October 21-24, 1991, Orlando, Florida.
B. L. Broadhead, Report of Foreign Travel to Scotland, England, France, ORNL/CSD/FTR-4066, October 1991.
B. L. Broadhead, "Criticality Safety Review of 2 ½-, 10-, and 14-Ton UF6 Cylinders," Int. Conf. on Nuclear Criticality Safety, September 9-13, 1991, Christ Church, Oxford, Great Britain; also see ORNL/TM-11947, Martin Marietta Energy Systems, Oak Ridge, National Laboratory, October 1991.
C. V. Parks, "Overview of the SCALE-4 Code System," in Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank,September 17-19, 1991, Saclay, France.
B. L. Broadhead, "An Overview of the QADS Code," pp. 163-174 in  Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, September 17-19, 1991, Saclay, France.
S. M. Bowman, "OFFSCALE: PC Input Processor for ORIGEN-S,"in Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, September 17-19, 1991, Saclay, France.
O. W. Hermann and C. V. Parks, "SAS2H: The SCALE-4 Analysis Sequence for LWR Fuel Depletion," in Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, September 17-19, 1991, Saclay, France.
L. M. Petrie, "Vectorization of the KENO V.a Criticality Safety Code,"  in Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, September 17-19, 1991, Saclay, France.
B. L. Broadhead and C. V. Parks,  "SCALE-4 Shipping Cask Shielding Applications," in Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, September 17-19, 1991, Saclay, France.
L. M. Petrie, N. F. Landers, N. M. Greene, and C. V. Parks, "New SCALE-4 Features Related to Cross-Section Processing," in Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, September 17-19, 1991, Saclay, France.
B. L. Broadhead, J. S. Tang, and C. V. Parks, "SAS1 and SAS4, Two New Shielding Analysis Sequences for Spent Fuel Casks," in Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, September 17-19, 1991, Saclay, France.
C. F. Weber, E. C. Beahm, and T. S. Kress,  "Iodine Chemical Forms in LWR Severe Accidents," pp. 414-430, NEA/ CSNI/R(91)15, JAERI, 1992 in Proc. 3rd CSNI Workshop on Iodine Chemistry in Reactor Safety, September 11-13, 1991, Tokai- Mura, Japan.
B. L. Broadhead, Feasibility Assessment of Burnup Credit in the Criticality Analysis of Shipping Casks with Boiling Water Reactor Spent Fuel, ORNL/CSD/TM-268, Martin Marietta Energy Systems, Oak Ridge National Laboratory, August 1991.
S. M. Bowman, Validation of SCALE-4 for a Reference Problem Set, ORNL/M-1332, Martin Marietta Energy Systems, Oak Ridge National Laboratory, July 1991.
O. W. Hermann, SAS2H Input and Assumptions for Cases Computing Isotopic Activities for Sequoyah Nuclear Plant, ORNL/M-1503, Martin Marietta Energy Systems, Oak Ridge National Laboratory, July 1991.
E. C. Beahm, C. F. Weber, T. S. Kress, and G. W. Parker, Iodine Chemical Forms in LWR Severe Accidents, Final Report,  NUREG/CR-5732 (ORNL/TM-11861/R3), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, July 1991.
H. R. Dyer, W. C. Jordan, and V. R. Cain, "A Technique for Code Validation for Criticality Safety Calculations," 1991 Annual Meeting American Nuclear Society, June 2-6, 1991, Orlando, Florida.  Trans. Am. Nucl. Soc., 63, 238-240 (1991).
T. S. Kress, E. C. Beahm, and C. F. Weber, "Fission Product Behavior," 1991 Annual Meeting American Nuclear Society, June 2-6, 1991, Orlando, Florida.  Trans. Am. Nucl. Soc.,   63, 260 (1991).
C. O. Slater, J. V, Pace, III, R. L. Childs, M. J. Haire, and T. Koyama, "Three-Dimensional Radiation Dose Mapping with TORT Computer Code," 1991 Annual Meeting American Nuclear Society, June 2-6, 1991, Orlando, Florida.  Trans. Am. Nucl. Soc., 63, 368-370 (1991).
B. L. Broadhead, S. Raman, and J. K. Dickens, "Measurement and Calculation of High Actinide Burnup in the Prototype Fast Reactor (PFR)," 1991 Annual Meeting American Nuclear Society, June 2-6, 1991, Orlando, Florida. Trans. Am. Nucl. Soc., 63, 88-89 (1991).
C. V. Parks, O. W. Hermann and B. L. Broadhead, "The SCALE Analysis Sequence for LWR Fuel Depletion," pp. 10.2 3.1 - 10.2 3-14 in  Proc. of ANS/ENS International Topical Meeting,April 28-May 1, 1991, Pittsburgh, Pennsylvania.
C. V. Parks, L. M. Petrie, J. Manneschmidt, and J. L. Bartley, "SCALE-4: An Updated Version of the Modular Code System for Performing Standardized Computer Analysis For Licensing Evaluation," Proc. of ANS/ENS Inter. Topical Meeting on Advances in Mathematics, Computations, and Reactor Physics, April 28-May 1, 1991, Pittsburgh, Pennsylvania.
W. A. Rhoades and R. L. Childs, "TORT - Three-Dimensional Oak Ridge Discrete Ordinates Neutron/Photon Transport Code," Proc. of ANS/ENS Inter. Topical Meeting on Advances in Mathematics, Computations, and Reactor Physics, April 28-May 1, 1991, Pittsburgh, Pennsylvania.
C. V. Parks,  Report of Foreign Travel, ORNL/CSD/FTR-3888, April  1991.
S. M. Bowman, Criticality Reference Benchmark Calculations for Burnup Credit Using Spent Fuel Isotopics, ORNL/M-1423, Martin Marietta Energy Systems, Oak Ridge National Laboratory, April 1991.
O. W. Hermann, Data Compiled in Burnup Credit Isotopic Validation Study,ORNL/M-1425, Martin Marietta Energy Systems, Oak Ridge National Laboratory, April 1991.
R. J. Raridon, J. E. Horwedel, and R. Q. Wright, "An Automated Sensitivity Analysis Procedure Applied to an Atmospheric Dispersion Model," Annu. Meet. Am. Assoc. Adv. Sci.,   February 14-19, 1991, Washington, D.C.


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