Oak Ridge National Laboratory

Nuclear Engineering Applications Section
1992

  Author(s) / Report Title / Publication Number / Date
Y. Y. Azmy, R. T. Santoro, M. B. Emmett, G. Hunt, C. M. Haaland, and T. J. Burns,  Monte Carlo Calculations and Postprocessing of Target Signatures for Smart Weapons Sensors, ORNL/M-2114, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1992.
E. C. Beahm, R. A. Lorenz, and C. F. Weber, Iodine Evolution and pH Control, NUREG/CR-5950 (ORNL/TM-12242), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1992.
R. L. Childs, Evaluation of Neutron Interaction Effects in the Recycle Equipment Test Facility (RETF), ORNL/CFRP-92/20, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1992.
J. E. Horwedel, R. J. Raridon, and R. Q. Wright, "Automated Sensitivity Analysis of an Atmospheric Dispersion Model," Atmos. Environ., 26A(9), 1643-1649 (1992).
R. Q. Wright, "Revised Hafnium Evaluations for ENDF/B-VI," Trans. Am. Nucl. Soc., 65,  422-424 (1992).
D. T. Ingersoll, R. Q. Wright, and C. O. Slater, "Phase II Testing of ENDF/B-VI Shielding Data," Trans. Am. Nucl. Soc., 65,  385-91 (1992).
W. C. Jordan and J. C. Turner,  Minimum Mass of Moderator Required for Criticality of Homogeneous Low-Enriched Uranium Systems, ORNL/CSD/TM-284, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1992.
W. A. Rhoades, R. A. Lillie, and M. B. Emmett,  Verification of MORSE-SGC on the Cray UNICOS System, ORNL/NPR-92/5, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1992.
W. A. Rhoades, R. L. Childs, and D. T. Ingersoll, "Radiation Exposure Inside Reinforced Concrete Buildings at Nagasaki," Health Phys,. 63(5), 510-21 (1992).
C. F. Weber, E. C. Beahm, and J. S. Watson, "Optimal Determination of Rate Coefficients in Multiple Reaction Systems," Comput. Chem., 16(4), 325-333 (1992).
W. C. Jordan and J. C. Turner, Estimated Critical Conditions for UO2F2-H20 Systems in Fully Water- Reflected Spherical Geometry, ORNL/TM-12292, Martin Marietta Energy Systems, Oak Ridge National Laboratory, December 1992.
B. L. Broadhead, R. L. Childs, R. M. Westfall, and C. V. Parks, Evaluation of Criticality Alarm Response at the WEMCO Fernald Site,ORNL/TM-12232, Martin Marietta Energy Systems, Oak Ridge National Laboratory,  November 1992.
R. T. Primm, C. M. Hopper, and G. R. Smolen, Criticality Safety Studies for the Storage of Waste from Nuclear Fuel Services in Intercell Storage Wells 2 and 3 of Building 3019, ORNL/TM-12152, Martin Marietta Energy Systems, Oak Ridge National Laboratory, November 1992.
J. E. White, R. Q. Wright, R. W. Roussin, and D. T. Ingersoll, Specifications for the Development of BUGLE-93: An ENDF/B-VI Multigroup Cross Section Library for LWR Shielding and Pressure Vessel Dosimetry, ORNL/TM-12230, Martin Marietta Energy Systems, Oak Ridge National Laboratory, November 1992.
B. L. Broadhead and C. V. Parks,  "Assessment of Dose Factor Changes to Spent Fuel Cask Analyses," in Proc. 1992 International Conference on Fifty Years of Controlled Nuclear Chain Reaction: Past Present, and Future, November 15-20, 1992, Chicago, Illinois.
E. C. Beahm, C. F. Weber, T. S. Kress, and G. W. Parker, "Iodine Chemical Forms in LWR Severe Accidents," pp. 325-42, in Proc. 19th Water Reactor Safety Information Meeting, October 28-30, 1991, Bethesda, Maryland, NUREG/CP-0119 (1992).
B. L. Broadhead, "Processing of Resonance Parameter Covariance Files," Proc. NEANSC Specialists' Meeting on Evaluation and Processing of Covariance Data, October 7-9, 1992, Oak Ridge, Tennessee.
R. E. Maerker, B. L. Broadhead, and J. J. Wagschal, "Needs for Evaluated Covariance Data for Reactor Pressure Vessel Dosimetry," p. 13-32 in Proc. NEANSC Specialists' Meeting on Evaluation and Processing of Covariance Data, October 7-9, 1992, Oak Ridge, Tennessee.
N. M. Greene, W. E. Ford III, L. M. Petrie, and J. W. Arwood, AMPX-77: A Modular Code System for Generating Coupled Multigroup Neutron-Gamma Cross-Section Libraries from ENDF/B-IV and/or ENDF/B-V, ORNL/CSD/TM-283, Martin Marietta Energy Systems, Oak Ridge National Laboratory, October 1992.
C. F. Weber, E. C. Beahm, and T. S. Kress, Models of Iodine Behavior in Reactor Containments, ORNL/TM-12202, Martin Marietta Energy Systems, Oak Ridge National Laboratory, October 1992.
C. V. Parks, Report of Foreign Travel to Vienna, Austria, ORNL/FTR-4376, September 1992.
C. Parks, H. Schweer, and C. Wilson, "Issues Concerning Criticality Safety and Overpacks in the Safe Transport of Radioactive Material," Report of Consultants Service Meeting, September 2-4, 1992, Vienna, Austria.
C. V. Parks, "Criticality Safety and Shielding Analysis Methods for Transport Packages," p. 13-32 in  Proc. of DOE Transportation Management Program Workshop, August 18-20, 1992, Gaithersburg, Maryland.
C. V. Parks, B. L. Broadhead, and M. C. Brady, "Status of Shielding Analysis Methods for Transport Packages," Vol. II, pp. 1650- 1653 in Proc. of IRPA8, May 17-22, 1992,  Montreal, Canada.
W. A. Rhoades, R. A. Lillie, and M. B. Emmett,  Transmission Factors for the Penetration of Neutron and Photon Fluence into Wood-Frame Dwellings, 1990 (TF90), ORNL/TM-12021, Martin Marietta Energy Systems, Oak Ridge National Laboratory, May 1992.
O. W. Hermann, C. V. Parks, and J.-P. Renier, "A Proposed Regulatory Guide Basis for Spent Fuel Decay Heat," Vol. 2, pp. 1662-1669 in  Proc. of the Third International Conference on High Level Radioactive Waste Management, April 12-16, 1992,  Las Vegas, Nevada.
S. M. Bowman, "ORIGNATE - PC Input Processor for ORIGEN-S," Vol. 1, p. 88-92 in Proc. of the Third International Conference on High Level Radioactive Waste Management, April 12-16, 1992,  Las Vegas, Nevada.
B. L. Broadhead, C. V. Parks, and R. B. Pope, "Assessment of Proposed Dose Factor Changes to Shipping Cask Design and Operation," Vol. 2, pp. 2174-2181 in Proc. of the Third International Conference on High Level Radioactive Waste Management, April 12-16, 1992,  Las Vegas, Nevada.
B. L. Broadhead, C. V. Parks, D. S. Joy, and J. S. Tang, "Preliminary Assessment of the Benefits of Derating a Cask for Increasing Age/Burnup Capability," Vol. 2, pp. 2182-2189  in Proc. of the Third International Conference on High Level Radioactive Waste Management, April 12-16, 1992,  Las Vegas, Nevada.
O. W. Hermann and R. Salmon, "Borosilicate Glass (a,n) Sources Used with ORIGEN-Type Calculations," Vol. 2, pp. 1662-1669 in Proc. of the Third International Conference on High Level Radioactive Waste Management, April 12-16, 1992,  Las Vegas, Nevada.
C. V. Parks,  "Overview of ORIGEN2 and ORIGEN-S: Capabilities and Limitations," Vol. 1, pp. 57-63  in Proc. of the Third International Conference on High Level Radioactive Waste Management, April 12-16, 1992,  Las Vegas, Nevada.
S. Raman, B. L. Broadhead, J. K. Dickens, R. L. Walker, and J. L. Botts,  Analyses of Physics Specimens in Fuel Pins 1 and 2 Irradiated in the Dounreay Prototype Fast Reactor, ORNL/6632, Martin Marietta Energy Systems, Oak Ridge National Laboratory, January 1992.


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