# Reactor and Nuclear Systems Division

1970 - 1979 Publications

[1970] [1971] [1972] [1973] [1974] [1975] [1976] [1977] [1978] [1979]

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.

**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.

**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.

**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**, "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.

**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.

**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.

**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).

**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.

**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.