# Nuclear Science

#
1970-79 Publications

R. L. Childs et al., Sensitivity and Uncertainty Analysis for the Mixed-Oxide Thermal Lattice U-L212 , ORNL/TM-6868, Union Carbide Corp. (Nuclear Division), Oak Ridge National Laboratory, 1979.

C. F. Weber and E. M. Oblow, Sensitivity Theory Applied to a Transient Thermal-Hydraulic Problem, ORNL/TM-6900, Union Carbide Corp., Oak Ridge National Laboratory, 1979.

R. M. Westfall, "Methods Development for Criticality Safety Analysis," Trans. Am. Nucl. Soc. 33, 361-2 (1979).

J. A. Bucholz and R. M. Westfall, "Reactivity Effect of Cross-Section Processing for Moist Bulk-Oxide Criticals," Trans. Am. Nucl. Soc. 33, 368-72 (1979).

M. J. Lorek, H. L. Dodds, L. M. Petrie, and R. M. Westfall, "Improved Criticality Search Techniques for Low and High Enriched Systems," Trans. Am. Nucl. Soc. 33, 372-4 (1979).

R. E. Pevey, H. L. Dodds, N. M. Greene, and R. M. Westfall, "On the Proper Use of the Nordheim Integral Treatment for Resonance Processing," Trans. Am. Nucl. Soc. 33, 353-4 (1979).

R. M. Westfall and J. R. Knight, "SCALE System Cross Section Validation with Shipping-Cask Critical Experiments," Trans. Am. Nucl. Soc. 33, 368 (1979).

R. M. Westfall, J. T. West, G. E. Whitesides, and J. T. Thomas, Criticality Analyses of Disrupted Core Models of Three Mile Island Unit 2, ORNL/CSD/TM-106, Union Carbide Corp. (Nuclear Division), Oak Ridge National Laboratory, 1979.

J. T. West, L. M. Petrie, and S. K. Fraley, KENO-IV/CG, The Combinatorial Geometry Version of the KENO: Monte Carlo Criticality Safety Program, NUREG/CR-0709 (ORNL/UREG/CSD-7), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, September 1979.

V. R. Cain and M. B. Emmett, BREESE-II: Auxiliary Routines for Implementing the Albedo Option in the MORSE Monte Carlo Code, ORNL/TM-6807, Oak Ridge National Laboratory, July 1979.

G. E. Whitesides and R. M. Westfall, Quarterly Progress Report on Review of Critical Experiments Performed for Fuel Cycle Safety Guidance for Period July 1, 1979 to September 30, 1979, ORNL/CSD/INF-79/11, Union Carbide Corp. (Nuclear Division), Oak Ridge National Laboratory, 1979.

G. E. Whitesides and R. M. Westfall, Quarterly Progress Report on Review of Critical Experiments Performed for Fuel Cycle Safety Guidance April 1, 1979 to June 30, 1979, ORNL/CSD/INF-79/8, Union Carbide Corp. (Nuclear Division), Oak Ridge National Laboratory, 1979.

R. M. Westfall and M. A. Bjerke, "An Interface-Currents Integral Transport Model for Treating Doubly-Heterogeneous, Multisystem Geometries," Proc. of the Topical Meeting on Computation Methods in Nuclear Engineering, Williamsburg, Virginia, pp. (7)71-8311, CONF-790402-17, April 1979.

B. L. Broadhead and J. H. Marable, "Sensitivity and Uncertainty Analysis Applied to the NBS-ISNF," A Review of the Theory and Application of Sensitivity and Uncertainty Analysis, Proc. of a Seminar-Workshop, Oak Ridge, Tenn., August 22-24, 1978, ORNL/RSIC-42, pp. 161-178, February 1979.

G. E. Whitesides and R. M. Westfall, Program for the Standardized Analysis of Fuel Shipping Containers - Quarterly Summary January 1, 1979 to March 31, 1979, ORNL/CSD/INF-79/5, Union Carbide Corp. (Nuclear Division), Oak Ridge National Laboratory, 1979.

G. E. Whitesides and R. M. Westfall, Program for the Review of Critical Experiments Performed for Fuel Cycle Safety Guidance - Quarterly Summary January 1, 1979 to March 31, 1979, ORNL/CSD/INF-79/6, Union Carbide Corp. (Nuclear Division), Oak Ridge National Laboratory, 1979.

W. A. Rhoades, D. B. Simpson, R. L. Childs, and W. W. Engle, Jr., The DOT-IV Two-Dimensional Discrete Ordinates Transport Code with Space-Dependent Mesh and Quadrature, ORNL/TM-6529, Union Carbide Corp., Oak Ridge National Laboratory, January 1979.

G. E. Whitesides and R. M. Westfall, Quarterly Progress Report on Review of Critical Experiments Performed for Fuel Cycle Safety Guidance - October 1, 1978 to December 31, 1978, ORNL/CSD/INF-79/2, Union Carbide Corp. (Nuclear Division), Oak Ridge National Laboratory, 1979.

G. E. Whitesides and R. M. Westfall, Quarterly Report on Program for the Standardized Analysis of Fuel Shipping Containers - Quarterly Summary, October 1, 1978 to December 31, 1978, ORNL/CSD/INF-79/4, Union Carbide Corp. (Nuclear Division), Oak Ridge National Laboratory, 1979.

G. E. Whitesides and R. M. Westfall, Quarterly Progress Report on Review of Critical Experiments Performed for Fuel Cycle Safety Guidance, ORNL/CSD/INF-78/12, Union Carbide Corp., Oak Ridge National Laboratory (1978).

R. M. Westfall, "Standardized Cask Analysis and Correlation with Experiment," Trans. Am. Nucl. Soc. 28, 299-300 (1978).

T. J. Hoffman, S. K. Fraley, R. M. Westfall, and L. M. Petrie, "Monte Carlo Radioactive Heat Transfer for Spent-Fuel Shipping Casks," Trans. Am. Nucl. Soc. 28, 262-3 (1978).

M. B. Emmett and W. A. Rhoades, CARP, A Computer Code and Albedo Data Library for Use by BREESE, the MORSE Albedo Package, ORNL/TM-6503, Union Carbide Corp., Oak Ridge National Laboratory, October 1978.

R. M. Westfall and L. M. Petrie, "Standardized Safety Analysis of Nuclear Fuel Shipping Containers," pp. 842-849 in Proc. of the Fifth International Symposium on Packaging and Transportation of Radioactive Materials, May 7-12, 1978, Las Vegas, NV.

R. M. Westfall, "Resolved Resonance Processing in the Ampx Modular Code System," RSIC Seminar-Workshop Multigroup Nuclear Cross-Section Preparation, March 14-16, 1978, Oak Ridge, Tenn.

R. M. Westfall, W. E. Ford, and C. C. Webster, "Design Criteria for the 218 Group Criticality Safety Reference Library," RSIC Seminar-Workshop Multigroup Nuclear Cross-Section Preparation, March 14-16, 1978, Oak Ridge, Tenn.

N. M. Greene et al., "AMPX: A Modular System for Multigroup Cross-Section Generation and Manipulation," Proc. Seminar-Workshop, A Review of Multigroup Nuclear Cross Section Processing, Oak Ridge, Tenn., ORNL/RSIC-41, pp. 9-2211, March 1978.

N. F. Cross, R. M. Westfall, K. R. Turnbull, and P. B. Fox, "Validation of Criticality Safety Broad Group Library Using Uranium Systems," Trans. Am. Nucl. Soc. 27, 406-407 (1977).

W. W. Engle, Jr., F. R. Mynatt, M. B. Emmett, and M. L. Williams, "A Summary of the ORNL Shield Design Supporting Analysis for the FFTF," Proc. of the Fifth International Conference on Reactor Shielding (April 1977).

C. O. Slater and M. B. Emmett, "Analysis of a Fuel-Pin Neutron-Streaming Experiment to Test Methods for Calculating Neutron Damage to the GCFR Grid Plate," Proc. of Fifth International Conference on Reactor Shielding (April 1977).

W. E. Ford, C. C. Webster, and R. M. Westfall, A 218-Group Neutron Cross-Section Library in the AMPX Master Interface Format for Criticality Safety Studies, ORNL/CSD/TM-4, Union Carbide Corp., (Nuclear Division), Oak Ridge National Laboratory, 1976.

H. W. Bertini, R. T. Santoro, and O. W. Hermann, "Calculated Nucleon Spectra at Several Angles from 192-, 500-, 700-, and 900-MeV Carbon-12 on Iron-56," Phys. Rev. C 14, 590-595 (1976).

R. L. Childs and M. B. Emmett, Analysis of the TSF Three-Dimensional Stored-Fuel Experiment for the CRBR, ORNL-5187, Union Carbide Corp., Oak Ridge National Laboratory, September 1976.

W. W. Engle, Jr., M. B. Emmett, L. S. Abbott, and F. R. Mynatt, Review of ORNL Radiation Shielding Analyses of the Fast Flux Test Facility Reactor (1975-1976), ORNL-5166, Union Carbide Corp., Oak Ridge National Laboratory, June 1976.

J. S. Tang, P. N. Stevens, and T. J. Hoffman, Methods of Monte Carlo Biasing Using Two-Dimensional Discrete Ordinates Adjoint Flux, ORNL/TM-5414, Union Carbide Corp., Oak Ridge National Laboratory, June 1976.

M. B. Emmett, The MORSE Monte Carlo Radiation Transport Code System, ORNL-4972, Union Carbide Corp., Oak Ridge National Laboratory, 1975.

R. T. Santoro, H. W. Bertini, T. A. Gabriel, N. M. Larson, and O. W. Hermann, Operating Instructions for the Heavy-Ion Code HIC-1, ORNL/TM-4791,Union Carbide Corp., Oak Ridge National Laboratory, 1975.

R. M. Westfall, D. M. Plaster, W. E. Ford, and R. H. Odegaarden, "Procedure for Determining Broad Group Energy Structure for Criticality Safety Calculations," Trans. Am. Nucl. Soc. 22, 291-292 (1975).

W. W. Engle, Jr., M. B. Emmett, and M. L. Williams, "Analysis of the Complex Reactor Cavity Shield in the FTR," Trans. Am. Nucl. Soc. 22, 783-784 (1975).

W. E. Ford, R. M. Westfall, and C. C. Webster, "A 218 Neutron Group Master Cross Section Library for Criticality Safety Studies," Trans. Am. Nucl. Soc. 22, 290-291 (1975).

J. R. Knight and L. M. Petrie, 16 and 123 Group Weighting Functions for KENO, ORNL/TM-4660, Union Carbide Corp., Oak Ridge National Laboratory, November 1975.

L. M. Petrie and N. F. Cross, KENO IV - An Improved Monte Carlo Criticality Program, ORNL-4938, Union Carbide Corp., Oak Ridge National Laboratory, November 1975.

R. M. Westfall, "Cosine Current Transmission Probabilities for Spherical Shells," Trans. Am. Nucl. Soc. 18, 147 - 148 (1974).

R. M. Westfall, Extension of Case’s Method in the Two-Region Critical Cylinder and its Application as an Analytic Standard (Space Power Reactor), Dissertation, University of Virginia (1974).

W. A. Rhoades, M. B. Emmett, G. W. Morrison, J. V. Pace, and L. M. Petrie, Vehicle Code System (VCS) User's Manual, ORNL/TM-4648, Union Carbide Corp., Oak Ridge National Laboratory, 1974.

R. M. Westfall and D. R. Metcalf, "Singular Eigenfunction Solution of the Monoenergetic Neutron Transport Equation for Finite Radially Reflected Critical Cylinders," Nucl. Sci. Eng. 52, 1 - 11 (September 1973).

M. B. Emmett, C. E. Burgart, and T. J. Hoffman, DOMINO, A General Purpose Code for Coupling Discrete Ordinates and Monte Carlo Radiation Transport Calculations, ORNL-4853, Union Carbide Corp., Oak Ridge National Laboratory, July 1973.

M. B. Emmett, W. W. Engle, Jr., and F. R. Mynatt, "Calculation of Penetrations in the FTR Radial Cavity Shield," Trans. Am. Nucl. Soc. 17, 561-62 (1973).

R. M. Westfall and D. R. Metcalf, "Exact Solution of the Transport Equation for Critical Cylindrical Configurations," Trans. Am. Nucl. Soc. 15, 266 - 267 (June 1972).

C. E. Burgart and M. B. Emmett, Monte Carlo Calculations of the Response Functions of Bonner Ball Neutron Detectors, ORNL/TM-3739, Union Carbide Corp., Oak Ridge National Laboratory, 1972.

M. B. Emmett, C. E. Burgart, and T. J. Hoffman, "DOMINO -- A General Purpose Discrete Ordinates to Monte Carlo Code for Radiation Transport," New Developments in Reactor Physics and Shielding, Natl. Top. Mtg., Kiasesha Lake, NY, Bk. 1, pp. 499-511, CONF-720901.

E. A. Straker, R. L. Childs, and M. B. Emmett, Applications of DOT-MORSE Coupling to the Analysis of 3-D SNAP Shielding Problems, ORNL/TM-3365, Union Carbide Corp., Oak Ridge National Laboratory, 1971.

E. A. Straker and M. B. Emmett, Collision Site Plotting Routines and Collision Density Fluence Estimates for the MORSE Monte Carlo Code, ORNL/TM-3585, Union Carbide Corp., Oak Ridge National Laboratory, 1971.

E. A. Straker, J. V. Pace, M. B. Emmett et al., Penetration into a Missile Silo of Neutrons and Secondary Gamma Rays Produced by Point Isotropic Neutron Sources, ORNL/TM-3599, Union Carbide Corp., Oak Ridge National Laboratory, 1971 (classified).

E. A. Straker and M. B. Emmett, MORSEC, A Revised Cross-Section Module for the MORSE Multigroup Monte Carlo Code, ORNL-4716, Union Carbide Corp., Oak Ridge National Laboratory, September 1971.

M. B. Emmett, INTRIGUE-II, An IBM-360 Subroutine Package for Making Linear, Logarithmic and Semilogarithmic Graphs Using the Calcomp Plotter, ORNL-4664, Union Carbide Corp., Oak Ridge National Laboratory, March 1971.

G. P. Lahti and R. M. Westfall, Multigroup Resonance-Region Cross Sections for Tungsten and Depleted Uranium for Use in Shielding Calculations, NASA-TM-X-1909, National Aeronautics and Space Administration (1970).

M. B. Emmett, E. A. Straker, and M. L. Gritzner, Neutron and Secondary Gamma-Ray Induced Heat in the Ground Due to Point 12.2-15 MeV and Fission Sources at an Altitude of 50 Feet, ORNL-4626, Union Carbide Corp., Oak Ridge National Laboratory, November 1970.