Oak Ridge National Laboratory

Nuclear Engineering Applications Section
1994

  Author(s) / Report Title / Publication Number / Date
C. M. Hopper, "Department of Energy Plutonium ES&H Vulnerability Assessment Oak Ridge Site Assessment Team Report." 
B. Basoglu, R. W. Brewer, C. F. Haught, D. F. Hollenbach, A. D. Wilkinson, H. L. Dodds, and P. F. Pasqua, "Simulation of Hypothetical Criticality Accidents Involving Homogeneous Damp Low-Enriched UO2 Powder Systems,"; Nucl. Technol., 105, 14 (1994).
C. F. Haught, B. Basoglu, R. W. Brewer, D. F. Hollenbach, A. D. Wilkinson, H. L. Dodds, and R. L. Oxenham,  "Criticality Safety Analysis of a Calciner Exit Chute," Nucl. Technol., 105, 3 (1994).
D. F. Hollenbach, L. M. Petrie, and H. L. Dodds,  "Vectorization Methods Development for a New Version of the KENO V.a Criticality Safety Code,"  Nucl. Sci. Eng., 116(3),  147-164, (1994).
B. L. Broadhead,  Report of Foreign Travel to Vienna, ORNL/FTR-5266, December 1994.
C. M. Hopper, "DOE Spent Nuclear Fuel - Nuclear Criticality Safety Challenges and Safeguards Initiatives," in  Proc. Am. Nucl. Soc. Top. Mtg. on DOE Spent Nuclear Fuel Challenges and Initiatives, December 13-16, 1994, Salt Lake City, Utah.
S. M. Bowman,  OFFSCALE: A PC Input Processor for the SCALE Code System, The CSASIN Processor for the Criticality Sequences, NUREG/CR-6182, Vol. 1 (ORNL/TM-12663/V1), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, November 1994.
S. M. Bowman, OFFSCALE: A PC Input Processor for the SCALE Code System, The ORIGNATE Processor for ORIGEN-S, NUREG/CR-6182, Vol. 2 (ORNL/TM-12263/V2),  U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, November 1994.
C. V. Parks,  Report of Foreign Travel,  ORNL/FTR-5196, October 1994.
O. W. Hermann, J. P. Renier, and C. V. Parks, Technical Support for a Proposed Decay Heat Guide Using SAS2/ORIGEN-S Data, NUREG/CR-5625 (ORNL-6698), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, September 1994.
M. D. DeHart and S. M. Bowman, Validation of the SCALE Broad Structure 44-Group ENDF/B-V Cross-Section Library for Use in Criticality Safety Analyses, NUREG/CR-6102 (ORNL/TM-12460), U. S. Nuclear Regulatory Commission, September 1994.
OW Hermann,  SAS2H Input for Computing Core Activities of 4.5, 5.0, and 5.5 Weight % 235U Fuel for Sequoyah Nuclear Plant, ORNL/M-3739, Martin Marietta Energy Systems, August 1994.
N. M. Greene, J. W. Arwood, C. V. Parks, and R. Q. Wright,  The LAW Library - A Multigroup Cross-Section Library for Use in Radioactive Waste Analysis Calculations, ORNL/TM-12370, Martin Marietta Energy Systems, Oak Ridge National Laboratory, August 1994.
B. W. Moran and B. D. Murphy,  Assessment of Technical Criteria for the Termination of IAEA Safeguards on Nuclear Material Contained in Irradiated Waste (U),  K/NSP-217.
B. L. Broadhead, R. L. Childs, and R. M. Westfall,  "Evaluation of Fernald Plant 6 Criticality Alarm Response,"1994 Annual Meeting American Nuclear Society, June 19-23, 1994, New Orleans, Louisiana.   Trans. Am. Nucl. Soc., 70,  206-208, (1994).
C. F. Haught, B. Basoglu, R. W. Brewer, H. L. Dodds, and W. C. Jordan,  "Analysis of Hypothetical Criticality Excursion Accidents in 10-MW and 20-MW Freezer/Sublimerse," 1994 Annual Meeting American Nuclear Society, June 19-23, 1994, New Orleans, Louisiana. Trans. Am. Nucl. Soc., 70,  187-188 (1994).
H. L. Dodds, C. M. Hopper, J. T. Mihalczo, J. T. Thomas, and R. M. Westfall,  "Nuclear Criticality Safety Courses at the University of Tennessee- Knoxville," 1994 Annual Meeting American Nuclear Society, June 19-23, 1994, New Orleans, Louisiana.   Trans. Am. Nucl. Soc., 70,  34-35 (1994).
L. C. Leal, O. W. Hermann, and C. V. Parks,  "Automatic Rapid Processing SCALE/SAS2H-Produced Parameter- Dependent Cross Sections for ORIGEN-S,"1994 Annual Meeting American Nuclear Society, June 19-23, 1994, New Orleans, Louisiana.   Trans. Am. Nucl. Soc., 70,  356-358, (1994).
B. D. Murphy, S. Raman, J. K. Dickens, R. L. Walker and T. D. Newton,  "Transmutation Data for Actinide Samples Exposed in the Dounreay Prototype Fast Reactor," 1994 Annual Meeting American Nuclear Society, June 19-23, 1994, New Orleans, Louisiana. Trans. Am. Nucl. Soc., 70, 89-91 (1994).
D. F. Hollenbach and C. M. Hopper,  "Criticality Safety Study of the MSRE Fuel Drain Tank Cell," 1994 Annual Meeting American Nuclear Society, June 19-23, 1994, New Orleans, Louisiana. Trans. Am. Nucl. Soc., 70,  213-215 (1994).
A. Wilkinson, B. Basoglu, C. Bentley, M. Dunn, M. Plaster, T. Yamamoto, H. Dodds, and C. Hopper,  "Improved Dose Estimates for Nuclear Criticality Accidents: Preliminary Results," 1994 Annual Meeting American Nuclear Society, June 19-23, 1994, New Orleans, Louisiana.   Trans. Am. Nucl. Soc., 70,  213-215 (1994).
T. Suto, S. M. Bowman, and C. V. Parks, "The Reactivity Effects of Nuclide Buildup and Decay During Long-Term Fuel Storage," 1994 Inter. High Level Radioactive Waste Management Conference, May 22-27, 1994, Las Vegas, Nevada. 
R. M. Westfall,  "Nulcear Data for Criticality Safety," in Proc. Int. Conf. on Nuclear Data for Science and Technology, May 9-13, 1994, Gatlinburg, Tennessee.
R. W. Roussin, E. Menapace, S. Ganesan, N. M. Greene, A. Hasagawa, R. E. MacFarlane, V. N. Manokhin, M. Mattes, G. C. Panini, H. Takano, J. E. White, R. Q. Wright,  "International Evaluation Cooperation Subgroup 7/Multigroup Cross- Section Processing: Progress and New Directions," in Proc. Int. Conf. on Nuclear Data for Science and Technology, May 9-13, 1994, Gatlinburg, Tennessee.
B. D. Murphy, S. Raman, J. K. Dickens, R. L. Walker, and T. D. Newton,  "Fission-Product Data Analysis from Actinide Samples Exposed in the Dounreay Prototype Fast Reactor," in Proc. Int. Conf. on Nuclear Data for Science and Technology, May 9-13, 1994, Gatlinburg, Tennessee.
J. E. White, R. Q. Wright, D. T. Ingersoll, R. W. Roussin, N. M. Greene, and R. E. MacFarlane, "VITAMIN-B6: A Fine-Group Cross Section Library Based on ENDF/B- VI for Radiation Transport Applications," p. 733-736 in Proc. Int. Conf. on Nuclear Data for Science and Technology, May 9-13, 1994, Gatlinburg, Tennessee.
R. Q. Wright, J. E. White, and D. T. Ingersoll,  "Fast and Thermal Reactor Data Testing of ENDF/B-VI,"in Proc. Int. Conf. on Nuclear Data for Science and Technology, May 9-13, 1994, Gatlinburg, Tennessee.
D. F. Hollenbach, N. F. Landers, and L. M. Petrie,  "KENO Developments," p. 103  in LA-13277-C, in Proc. of Annu. Nucl. Crit. Tech. Safety Project, May 10-11, 1994, Williamsburg, Virginia.
W. C. Jordan, L. M. Petrie, R. Q. Wright, and C. V. Parks,  "Calculation of kinfinity for Homogeneous235U Metal Mixtures: Will the Real kinfinity Please Stand Up?" pp. 29-31 in LA-13277-C, Proc. of Annu. Nucl. Crit. Tech. Safety Project, May 10-11, 1994, Williamsburg, Virginia.
B. L. Broadhead, H. F. Locke, and A. Avery,  "NEACRP Comparison of Source Term Codes for the Radiation Protection Assessment of Transportation Packages," p. 738-745 in  Proc. 8th International Conference on Radiation Shielding, April 24-28, 1994, Arlington, Texas.
H. Taniuchi and B. L. Broadhead,  "Simple Geometry Dose Rate Benchmarks for Spent Fuel Cask Analysis," Proc. 8th International Conference on Radiation Shielding, April 24-28, 1994, Arlington, Texas.
E. C. Beahm and C. F. Weber, "Sludge Washing and Dissolution of ORNL Melton Valley Storage Tank (MVST) Waste," DOE Sludge Workshop, April 11-13, 1994, Hanford, Washington.
R. M. Westfall,  Report of Foreign Travel to France, ORNL/FTR-4938, April  1994.
C. V. Parks,  Report of Foreign Travel, ORNL/FTR-4914, March 1994.
P. Cousinou, C. Parks, H. Sannen, H. Schweer, and C. Wilson,  "Report of Consultation Meeting on Criticality Safety in the Transport of Radioactive Material," February 14-16, 1994, Vienna, Austria.
E. C. Beahm and C. F. Weber, "Sludge Washing and Dissolution of ORNL Melton Valley Storage Tank (MVST) Waste, "Efficient Separations and Processing Integrated Program (ESPIP) Meeting, January 10-11, 1994, Dallas, Texas.
E. C. Beahm, . F. Weber, J. L. Collins, C. W. Chase, A. Boatman, and R. J. Weaver,  "Sludge Dissolution/Leaching - ORNL," Efficient Separations and Processing Integrated Program (ESPIP) Meeting, January 10-11, 1994, Dallas, Texas.
D. F. Hollenbach and C. M. Hopper, Criticality Safety Study of the MSRE Fuel Drain Tank Cell in Building 7503, ORNL/TM-12642, Martin Marietta Energy Systems, Oak Ridge National Laboratory, January 1994.


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