Quick Links  1970  1971  1972  1973  1974  1975  1976  1977  1978  1979 
Author(s) / Report Title / Publication Number / Date  

1970  
G. P. Lahti and R. M. Westfall, Multigroup ResonanceRegion Cross Sections for Tungsten and Depleted Uranium for Use in Shielding Calculations, NASATMX1909, National Aeronautics and Space Administration (1970).  
M. B. Emmett, E. A. Straker, and M. L. Gritzner, Neutron and Secondary GammaRay Induced Heat in the Ground Due to Point 12.215 MeV and Fission Sources at an Altitude of 50 Feet, ORNL4626, Union Carbide Corp., Oak Ridge National Laboratory, November 1970.  
1971  
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, New York, Bk. 1, pp. 499511, CONF720901.  
E. A. Straker, R. L. Childs, and M. B. Emmett, Applications of DOTMORSE Coupling to the Analysis of 3D SNAP Shielding Problems, ORNL/TM3365, 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/TM3585, 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/TM3599, Union Carbide Corp., Oak Ridge National Laboratory, 1971 (classified).  
E. A. Straker and M. B. Emmett, MORSEC, A Revised CrossSection Module for the MORSE Multigroup Monte Carlo Code, ORNL4716, Union Carbide Corp., Oak Ridge National Laboratory, September 1971.  
M. B. Emmett, INTRIGUEII, An IBM360 Subroutine Package for Making Linear, Logarithmic and Semilogarithmic Graphs Using the Calcomp Plotter, ORNL4664, Union Carbide Corp., Oak Ridge National Laboratory, March 1971.  
1972  
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/TM3739, Union Carbide Corp., Oak Ridge National Laboratory, 1972.  
1973  
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, ORNL4853, 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, 56162 (1973).  
1974  
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 TwoRegion 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/TM4648, Union Carbide Corp., Oak Ridge National Laboratory, 1974.  
1975  
M. B. Emmett, The MORSE Monte Carlo Radiation Transport Code System, ORNL4972, 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 HeavyIon Code HIC1, ORNL/TM4791, 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, 291292 (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, 783784 (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, 290291 (1975).  
J. R. Knight and L. M. Petrie, 16 and 123 Group Weighting Functions for KENO, ORNL/TM4660, Union Carbide Corp., Oak Ridge National Laboratory, November 1975.  
L. M. Petrie and N. F. Cross, KENO IV  An Improved Monte Carlo Criticality Program, ORNL4938, Union Carbide Corp., Oak Ridge National Laboratory, November 1975.  
1976  
W. E. Ford, C. C. Webster, and R. M. Westfall, A 218Group Neutron CrossSection Library in the AMPX Master Interface Format for Criticality Safety Studies, ORNL/CSD/TM4, 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 900MeV Carbon12 on Iron56," Phys. Rev. C 14, 590595 (1976).  
R. L. Childs and M. B. Emmett, Analysis of the TSF ThreeDimensional StoredFuel Experiment for the CRBR, ORNL5187, 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 (19751976), ORNL5166, 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 TwoDimensional Discrete Ordinates Adjoint Flux, ORNL/TM5414, Union Carbide Corp., Oak Ridge National Laboratory, June 1976.  
1977  
N. F. Cross, R. M. Westfall, K. R. Turnbull, P. B. Fox, "Validation of Criticality Safety Broad Group Library Using Uranium Systems," Trans. Am. Nucl. Soc. 27, 406407 (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 Fifth International Conference on Reactor Shielding, (April 1977).  
C. O. Slater and M. B. Emmett, "Analysis of a FuelPin NeutronStreaming Experiment to Test Methods for Calculating Neutron Damage to the GCFR Grid Plate," Proc. of Fifth International Conference on Reactor Shielding, (April 1977).  
1978  
G. E. Whitesides and R. M. Westfall, Quarterly Progress Report on Review of Critical Experiments Performed for Fuel Cycle Safety Guidance, ORNL/CSD/INF78/12, Union Carbide Corp., Oak Ridge National Laboratory, 1978.  
R. M. Westfall, "Standardized Cask Analysis and Correlation with Experiment," Trans. Am. Nucl. Soc. 28, 299300 (1978).  
T. J. Hoffman, S. K. Fraley, R. M. Westfall, and L. M. Petrie, "Monte Carlo Radioactive Heat Transfer for SpentFuel Shipping Casks," Trans. Am. Nucl. Soc. 28, 2623 (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/TM6503, 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. 842849 in Proc. of the Fifth International Symposium on Packaging and Transportation of Radioactive Materials, May 712, 1978, Las Vegas, Nevada.  
R. M. Westfall, "Resolved Resonance Processing in the Ampx Modular Code System," RSIC SeminarWorkshop Multigroup Nuclear CrossSection Preparation, March 1416, 1978, Oak Ridge, Tennessee.  
R. M. Westfall, W. E. Ford, and C. C. Webster "Design Criteria for the 218 Group Criticality Safety Reference Library," RSIC SeminarWorkshop Multigroup Nuclear CrossSection Preparation, March 1416, 1978, Oak Ridge, Tennessee.  
N. M. Greene, W. E. Ford, L. M. Petrie, B. R. Diggs, C. C. Webster, J. L. Lucius, J. E. White, R. Q. Wright, and R. M. Westfall, "AMPX: A Modular System for Multigroup CrossSection Generation and Manipulation," Proc. SeminarWorkshop, A Review of Multigroup Nuclear Cross Section Processing, Oak Ridge, Tennessee, ORNL/RSIC41, pp. 92211, March 1978.  
1979  
R. L. Childs, G. de Saussure, J. L. Lucius, J. D. Drischler, V. C. Baker, J. H. Marable, R. M. Westfall, Sensitivity and Uncertainty Analysis for the MixedOxide Thermal Lattice UL212 , ORNL/TM6868, Union Carbide Corp. (Nuclear Division), Oak Ridge National Laboratory, 1979.  
C. F. Weber and E. M. Oblow, Sensitivity Theory Applied to a Transient ThermalHydraulic Problem, ORNL/TM6900, Union Carbide Corp., Oak Ridge National Laboratory, 1979.  
R. M. Westfall, "Methods Development for Criticality Safety Analysis," Trans. Am. Nucl. Soc. 33, 3612 (1979).  
J. A. Bucholz and R. M. Westfall, "Reactivity Effect of CrossSection Processing for Moist BulkOxide Criticals," Trans. Am. Nucl. Soc. 33, 36872 (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, 3724 (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, 3534 (1979).  
R. M. Westfall and J. R. Knight "SCALE System Cross Section Validation with ShippingCask 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/TM106, Union Carbide Corp. (Nuclear Division), Oak Ridge National Laboratory, 1979.  
J. T. West, L. M. Petrie, and S. K. Fraley, KENOIV/CG, The Combinatorial Geometry Version of the KENO: Monte Carlo Criticality Safety Program, NUREG/CR0709 (ORNL/UREG/CSD7), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, September 1979.  
V. R. Cain and M. B. Emmett, BREESEII: Auxiliary Routines for Implementing the Albedo Option in the MORSE Monte Carlo Code, ORNL/TM6807, , 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/INF79/11, 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/INF79/8, Union Carbide Corp. (Nuclear Division), Oak Ridge National Laboratory, 1979.  
R. M. Westfall and M. A. Bjerke "An InterfaceCurrents Integral Transport Model for Treating DoublyHeterogeneous, Multisystem Geometries," Proc. of the Topical Meeting on Computation Methods in Nuclear Engineering, Williamsburg, Virginia, pp. (7)718311, CONF79040217, April 1979.  
B. L. Broadhead and J. H. Marable "Sensitivity and Uncertainty Analysis Applied to the NBSISNF," A Review of the Theory and Application of Sensitivity and Uncertainty Analysis, Proc. of a SeminarWorkshop, August 2224, 1978, Oak Ridge, Tennessee, ORNL/RSIC42, pp. 161178, 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/INF79/5, 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/INF79/6, 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 DOTIV TwoDimensional Discrete Ordinates Transport Code with SpaceDependent Mesh and Quadrature, ORNL/TM6529, 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/INF79/2, 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/INF79/4, Union Carbide Corp. (Nuclear Division), Oak Ridge National Laboratory, 1979. 