CHARLES O. SLATER

PUBLICATIONS

2009

C. O. Slater, R. T. Primm III, D. A. Pinkston, D. H. Cook, D. L. Selby, P. D. Ferguson, J. A. Bucholz, and E. Popov, Measured and Calculated Heating and Dose Rates for the HFIR HB4 Beam Tube and Cold Source, ORNL/TM-2009/012, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2009.

2006

J. O. Johnson, C. O. Slater, and E. D. Blakeman, “Preliminary Investigation into Lunar Surface Power Reactor Shielding Strategies,” Trans. Am. Nucl. Soc. 95, 504-505 (2006).

J. O. Johnson, C. O. Slater, and E. D. Blakeman, “Preliminary Investigations into Lunar Surface Power Reactor Shielding Strategies,” pp. 319–321 in the Proc. of the American Nuclear Society’s 14th Biennial Topical Meeting of the Radiation Protection and Shielding Division, April 3–6, 2006, Carlsbad, New Mexico.

C. O. Slater, Development and Testing of the FALSTF3D Last-Flight Estimation Computer Code, ORNL/TM-2006/42, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2006.

C. O. Slater, D. L. Selby, J. A. Bucholz, J. L. Robertson, and M. L. Crow, “Shielding Calculations for the Upgrade of the HFIR HB2 Beam Line,” J. ASTM International 3(6), (2006).

2005

C. O. Slater and R. T. Primm, III, Calculation of Rabbit and Simulator Worth in the HFIR Hydraulic Tube and Comparison With Measured Values, ORNL/TM-2005/94, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2005.

C. O. Slater, D. L. Selby, J. A. Bucholz, J. L. Robertson, and M. L. Crow, “Shielding Calculations for the Upgrade of the HFIR HB2 Beam Line,” Proceedings of the Twelfth International Symposium on Reactor Dosimetry, Gatlinburg, Tenn., May 8-13, 2005.

2004

J. F. Walker, P. A. Taylor, R. D. Spence, C. O. Slater, D. D. Walker, D. F. Bickford, S. Y. Lee, S. E. Aleman, and L. L. Hamm, Small-Column Ion-Exchange Alternative to Remove 137Cs From Low-Curie Salt Waste: Summary of Phase 1, ORNL/TM-2003/287, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2004.

J. F. Birdwell, Jr., R. M. Counce, C. O. Slater, R. A. Pierce, and D. D. Walker, Conceptual Design of a Simplified Skid-Mounted Caustic-Side Solvent Extraction Process for Removal of Cesium from Savannah River Site High-Level Waste, ORNL/TM-2004/59, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2004.

2003

C. O. Slater, J. C. Gehin, and R. T. Santoro, A Study of the Effects of a Radiation Dispersal Device, ORNL/TM-2003/128, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2003.

2002

C. O. Slater, Analysis of the JASPER Axial Shield Experiment, ORNL/TM-2002/93, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2002.

2001

C. O. Slater, J. V. Pace III, and R. T. Santoro, Irradiation Effects for the Pulsed Fast Neutron Analysis (PFNA) Cargo Interrogation System, ORNL/TM-2000/352, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2001.

C. O. Slater, J. M. Barnes, J. O. Johnson, J. P. Renier, and R. T. Santoro, Coupling of MASH-MORSE Adjoint Leakages with Space- and Time-Dependent Plume Radiation Sources, ORNL/TM-2000/335, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2001.

2000

J. E. White, D. T. Ingersoll, R. Q. Wright, H. T. Hunter, C. O. Slater, N. M. Greene, R. E. McFarlane, and R. W. Roussin, Production and Testing of the Revised VITAMIN-B6 Fine-Group and the BUGLE-06 Broad-Group Neutron/Photon Cross-Section Libraries Derived From ENDF/B-VI.3 Nuclear Data, NUREG/CR-6214, Rev. 1 (ORNL/TM-6975/R1), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., April 2000.

Charles O. Slater and Hamilton T. Hunter, "Validation of the VITAMIN-B6 and BUGLE-96 Cross-Section Libraries for Moderate-Energy Neutron and Photon Transport Calculations," Nuclear Technology 129, 201-217 (February 2000).

H. T. Hunter, C. O. Slater, L. B. Holland, G. Tracz, W. J. Marshall, and J. L. Parsons, "Shielding Benchmark Computational Analysis," Proceedings of Radiation Protection for Our National Priorities, 240-247, (2000).

1998

C. O. Slater, J. V. Pace III, R. A. Lillie, D. B. Simpson, and Y. Y. Yugo, Analysis of the Y-12 Building 9720-5 Criticality Accident Alarm System Response for Several Accident Scenarios, ORNL/TM-13570, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 23, 1998 (Unclassified Controlled Nuclear Information).

C. O. Slater, R. A. Lillie, J. O. Johnson, and D. B. Simpson, "Coupling of Monte Carlo Adjoint Leakages With Three-Dimensional Discrete Ordinates Forward Fluences," Proceedings of the 1998 ANS Radiation Protection and Shielding Division Topical Conference: "Technologies for the New Century," Nashville, Tenn., April 19-23, 1998.

1997

C. O. Slater, D. K. Olsen, J. O. Johnson, R. A. Lillie, and T. A. Gabriel, Shielding Assessment for the Proposed HRIBF Upgrade to the National ISOL Facility, ORNL/TM-13366, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 1997.

C. O. Slater, D. K. Olsen, J. O. Johnson, R. A. Lillie, and T. A. Gabriel, "Shielding Assessment for the Proposed Upgrade of the Holifield Radioactive Ion Beam Facility (HRIBF) to the National Radioactive Ion Beam Isotope Separator On Line (NRIBISOL) Facility," Am. Nucl. Soc. Proceedings of the Topical Meeting on Nuclear Applications of Accelerator Technology, Albuquerque, NM, November 16-20, 1997.

D. B. Simpson, J. V. Pace, R. A. Lillie, and C. O. Slater, “Splicing Techniques Available with DOORS,” Trans. Am. Nucl. Soc. 77, 340-342, 1997.

1996

U. Fishcer, Y. Oyama, F. Maekawa, C. Konno, M. Wada, Y Makita, A. Takahashi, K. Ueki, K. Kosako, K. Hayashi, M. Youssef, H. Hunter, C. Slater, U. Fischer, F. Kappler, et al., "Benchmark Validation of the FENDL-1 Nuclear Data Library—A Coordinated International Effort," Fusion Technol. 30, Part 2B, 1093-1100, 1996.

H. T. Hunter, D. T. Ingersoll, R. W. Roussin, E. Satori, and C. O. Slater, "SINBAD: Shielding INtegral Benchmark Archive and Database," Proceedings of the 1996 Topical Meeting on Radiation Protection and Shielding 2, 1112-1119 (1996).

J. E. White, D. T. Ingersoll, C. O. Slater, and R. W. Roussin, "BUGLE-96: A Revised Multigroup Cross Section Library for LWR Applications Based on ENDF/B-VI Release 3", Proceedings of the 1996 Topical Meeting on Radiation Protection and Shielding 2, 1071-1079 (1996).

D. T. Ingersoll, C. O. Slater, E. L. Redmond II, and R. G. Zamenhof, "Comparison of TORT and MCNP Dose Calculations for BNCT Treatment Planning," Seventh International Symposium on Neutron Capture Therapy for Cancer, Zurich, Switzerland, September 4-7, 1996.

D. T. Ingersoll, C. O. Slater, and L. R. Williams, "BNCT Filter Design Studies for the ORNL Tower Shielding Facility," Seventh International Symposium on Neutron Capture Therapy for Cancer, Zurich, Switzerland, September 4-7, 1996.

D. T. Ingersoll, C. O. Slater, and L. R. Williams, "BNCT Filter Design Studies for the ORNL Tower Shielding Facility," Trans. Am. Nucl. Soc. 75, 28-30 (1996).

D. T. Ingersoll, C. O. Slater, E. L. Redmond II, and R. G. Zamenhof, "Comparison of TORT and MCNP Dose Calculations for BNCT Treatment Planning," Trans. Am. Nucl. Soc. 75, 36-37 (1996).

C. O. Slater, contribution for the analysis of the SB5 and SB6 fusion shielding benchmarks, in Integral Data Tests of the FENDL-1 Nuclear Data Library for Fusion Applications: Summary Report of the International Working Group on "Experimental and Calculational Benchmarks on Fusion Neutronics for FENDL Validation," U. Fischer, ed., Report FZKA 5785 or INDC(GER)-41, Forschungszentrum Karlsruhe (August 1996).

1995

D. T. Ingersoll, J. E. White, R. Q. Wright, H. T. Hunter, C. O. Slater, N. M. Greene, R. W. Roussin, and R. E. MacFarlane, Production and Testing of the VITAMIN-B6 Broad-Group Neutron/Photon Cross-Section Libraries Derived from ENDF/B-VI Nuclear Data, NUREG/CR-6214 (ORNL-6795), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., January 1995.

C. O. Slater and J. A. Bucholz, Global Shielding Analysis for the Three-Element-Core Advanced Neutron Source Reactor Under Normal Operating Conditions, ORNL/TM-13043, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 1995.

S.-H. Kim, V. Georgevich, D. B. Simpson, C. O. Slater, and R. P. Taleyarkhan, "Modeling and Analysis of Core-Debris Recriticality During Hypothetical Severe Accidents in the Advanced Neutron Source Reactor," Nucl. Safety 36(1), 58-67 (1995).

1994

J. V. Pace, III, C. O. Slater, and M. S. Smith, "Three-Dimensional Discrete Ordinates Radiation Transport Calculations of Neutron Fluxes for Beginning-of-Cycle at Several Pressure Vessel Surveillance Positions in the High Flux Isotope Reactor," Proceedings of the Eighth ASTM-EURATOM Symposium on Reactor Dosimetry, August 29, 1993–September 3, 1993, Vail, Colorado, Reactor Dosimetry ASTM STP 1228, Harry Farrar IV, E. Parvin Lippincott, John G. Williams, and David Vehar, Eds., American Society for Testing and Materials, Philadelphia, 140-146 (1994).

D. T. Ingersoll, J. E. White, R. Q. Wright, H. T. Hunter, C. O. Slater, N. M. Greene, R. E. McFarlane, "Production and Testing of the Vitamin B6 Fine-Group and the Bugle-93 Broad-Group Neutron/Photon Cross-Section Libraries Derived from ENDF/B-VI Nuclear Data," Proceedings of the Eighth ASTM-EURATOM Symposium on Reactor Dosimetry, August 29, 1993–September 3, 1993, Vail, Colorado, Reactor Dosimetry ASTM STP 1228, Harry Farrar IV, E. Parvin Lippincott, John G. Williams, and David Vehar, Eds., American Society for Testing and Materials, Philadelphia, 660-669 (1994).

C. O. Slater, R. A. Lillie, and T. A. Gabriel, "Shielding Optimization Studies for the Detector Systems of the Superconducting Super Collider," Proceedings of the 8th International Conference on Radiation Shielding 2, 972-979 (1994).

P. K. Job, T. Handler, T. A. Gabriel, C. O. Slater, L. S. Waters, A. P. Palounek, C. Zeitnitz, "Neutron Fluence Calculations for the SDC Detector and the Results of Codes Comparison," Proceedings of the 8th International Conference on Radiation Shielding 2, 980-984 (1994).

H. T. Hunter, C. O. Slater, and J. E. White, "BUGLE-93 (ENDF/B-VI) Cross-Section Library Data Testing Using Shielding Benchmarks," Proceedings of the 8th International Conference on Radiation Shielding2, 840-847 (1994).

H. T. Hunter, D. T. Ingersoll, R. W. Roussin, E. Satori, and C. O. Slater, "SINBAD - A Shielding Integral Benchmark Archive and Database for PC's," Proceedings of the 8th International Conference on Radiation Shielding 2, 795-801 (1994).

C. O. Slater, "Analysis of the JASPER Axial Shield Experiment," Proceedings of the 8th International Conference on Radiation Shielding 2, 1271-1278 (1994).

1993

C. O. Slater, Analysis of the JASPER Program Radial Shield Attenuation Experiment, ORNL/TM-10701, Oak Ridge National Laboratory, Oak Ridge, Tenn., January 1993.

R. P. Taleyarkhan, S. H. Kim, C. O. Slater, D. L. Moses, D. B. Simpson, and V. Georgevich, Modeling and Analysis of Core Debris Recriticality During Hypothetical Severe Accidents in the Advanced Neutron Source Reactor, ORNL/TM-12382, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 1993.

S. N. Cramer and C. O. Slater, "Investigation of Radiation Effects in Hiroshima and Nagasaki Using a General Monte Carlo-Discrete Ordinates Coupling Scheme," Nucl. Sci. Eng.114(1), 1-11 (1993).

R. P. Taleyarkhan, S. H. Kim, C. O. Slater, D. L. Moses, D. B. Simpson, and V. Georgevich, "Modeling and Analysis of Core Debris Recriticality During Hypothetical Severe Accidents in the Advanced Neutron Source Reactor," Proceedings of the 2nd ASME-JSME Nuclear Engineering Joint Conference, 471-479 (1993).

F. S. Alsmiller, R. G. Alsmiller, Jr., C. Y. Fu, T. A. Gabriel, R. A. Lillie, and C. O. Slater, "Radiation Levels in the SSC Experimental Facilities," Trans. Am. Nucl. Soc. 69, 433-436 (1993).

1992

C. O. Slater, DRC2: A Code with Specialized Applications for Coupling Localized Monte Carlo Adjoint Calculations with Fluences from Two-Dimensional R-Z Discrete Ordinates Air-Over-Ground Calculations, ORNL/TM-11873, Oak Ridge National Laboratory, Oak Ridge, Tenn., January 1992.

C. O. Slater, Analysis of the ANL Co-60 Facility TORT Code Verification Experiment, ORNL/TM-11931, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 1992.

D. T. Ingersoll, R. Q. Wright, and C. O. Slater, "Phase II Testing of ENDF/B-VI Shielding Data," Proceedings of the Topical Meeting on New Horizons in Radiation Protection and Shielding, 385-391 (1992).

1991

C. O. Slater, TORT Calculations of Dose Rates for Detailed Design Phase I Amendment of the Recycle Equipment Test Facility Main Process Cell, ORNL/CFRP-91/15, Oak Ridge National Laboratory, Oak Ridge, Tenn., November 1991.

C. O. Slater, Shielding Optimization Studies for the Recycle Equipment Test Facility Main Process Cell, ORNL/CFRP-91/24, Oak Ridge National Laboratory, Oak Ridge, Tenn., November 1991.

C. O. Slater, J. V. Pace III, R. L. Childs, M. J. Haire, and T. Koyama, "Three-Dimensional Radiation Dose Mapping with the TORT Computer Code," Trans. Am. Nucl. Soc. 63, 368-369 (1991).

1990

C. O. Slater, Analysis of the JASPER Fission Gas Plenum Experi­ment, ORNL/TM-10681, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 1990.

S. N. Cramer and C. O. Slater, Investigation of Radiation Effects in Hiroshima and Nagasaki Using a General Monte Carlo-Discrete Ordinates Coupling Scheme, ORNL/TM-11532, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 1990.

C. O. Slater, Two-Dimensional DORT Discrete Ordinates X-Y Geometry Neutron Flux Calculations for the Halden Heavy Boiling Water Reactor Core Configurations, ORNL/TM-11513, Oak Ridge National Laboratory, Oak Ridge, Tenn., July 1990.

W. E. Ford, III, J. W. Arwood, N. M. Greene, D. L. Moses, L. M. Petrie, R. T. Primm, III, C. O. Slater, R. M. Westfall, and R. Q. Wright, ANSL-V: ENDF/B-V Based Multigroup Cross-Section Libraries for Advanced Neutron Source (ANS) Reactor Studies, ORNL-6618, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 1990.

J. V. Pace, III, C. O. Slater, and D. T. Ingersoll, Analysis of Activation Products Generated During the JASPER In-Vessel Fuel Storage Experiment, ORNL/LMR/AC-90/5 (Applied Technology), Oak Ridge National Laboratory, Oak Ridge, Tenn., December 1990.

S. N. Cramer and C. O. Slater, "Investigation of Radiation Effects in Hiroshima and Nagasaki Using a General Monte Carlo-Discrete Ordinates Coupling Scheme," Trans. Am. Nucl. Soc. 61, 138 (1990).

K. Chatani and C. O. Slater, "Application of the Three-Dimension­al Transport Code to Analysis of the Neutron Streaming Experi­ment," Trans. Am. Nucl. Soc. 62, 442-444 (1990).

1989

D. T. Ingersoll, J. V. Pace, III, and C. O. Slater, Analysis of Activation Products Generated During the JASPER Program Axial Shield Experiment, ORNL/LMR/AC-90/3, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 1989.

R. Q. Wright, M. L. Williams, and C. O. Slater, "Impact of 235U (MAT 9235) Evaluation on K eff of Thermal Systems," Trans. Am. Nucl. Soc. 59, 343-344 (1989).

1988

W. W. Engle, Jr., R. A. Lillie, and C. O. Slater, "Radiation Transport Calculations for the ANS Beam Tubes," Trans. Am. Nucl. Soc. 57, 294-295 (1988).

1987

D. T. Ingersoll, W. W. Engle, Jr., F. J. Muckenthaler, and C. O. Slater, JASPER USDOE/PNC Shielding Research Program Technical Progress Report October 1–November 30, 1986, ORNL/LMR/AC-87/1, Oak Ridge National Laboratory, Oak Ridge, Tenn., January 1987.

D. T. Ingersoll, W. W. Engle, Jr., F. J. Muckenthaler, and C. O. Slater, JASPER USDOE/PNC Shielding Research Program Technical Progress Report December 1, 1986–January 31, 1987, ORNL/LMR/AC-87/2, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 1987.

C. O. Slater, Analysis of the ORNL/TSF Alternate Shielding Materials Experiment, ORNL/TM-10183, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 1987.

D. T. Ingersoll, W. W. Engle, Jr., F. J. Muckenthaler, and C. O. Slater, JASPER USDOE/PNC Shielding Research Program Technical Progress Report February 1–March 31, 1987, ORNL/LMR/AC-87/3, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 1987.

D. T. Ingersoll, W. W. Engle, Jr., F. J. Muckenthaler, and C. O. Slater, JASPER USDOE/PNC Shielding Research Program Technical Progress Report," ORNL/LMR/AC-87/4, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 1987.

D. T. Ingersoll, W. W. Engle, Jr., F. J. Muckenthaler, and C. O. Slater, JASPER USDOE/PNC Shielding Research Program Technical Progress Report for June 1July 31, 1987, ORNL/LMR/AC-87/5, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 1987.

C. O. Slater, F. J. Muckenthaler, and D. T. Ingersoll, "Experi­mental Verification of Calculated Neutron Streaming in the Bottom Reflector and Core Support Regions of a Large-Scale High-Temperature Gas-Cooled Reactor Design Concept," NSE 97, 123-144 (1987).

W. W. Engle, Jr., D. T. Ingersoll, C. O. Slater, and F. J. Muckenthaler, Specification for the JASPER Program Attenuation Experiment, ORNL/LMR/AC-86/5, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 1986.

D. T. Ingersoll, W. W. Engle, Jr., F. J. Muckenthaler, and C. O. Slater, JASPER USDOE/PNC Shielding Research Program Technical Progress Report August 1September 30, 1986, ORNL/LMR/AC-86/6, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 1986.

C. O. Slater, F. J. Muckenthaler, and D. T. Ingersoll, Experi­mental Verification of Calculated Neutron Streaming in the Bottom Reflector and Core Support Regions of the 2240-MW(t) HTGR Design Concept, ORNL/TM-10282 (also DOE/HTGR-86-131), Oak Ridge National Laboratory, Oak Ridge, Tenn., December 1986.

C. O. Slater, Analysis of Phase II of the HTGR Bottom Reflector and Core Support Block Neutron-Streaming Experiment, ORNL/TM-9485 (also HTGR-85-031), Oak Ridge National Laboratory, June 1985.

1985

C. O. Slater, Updated Analysis of the Core Support Plate, Cross Duct, and Lower Vessel Regions of the Modular Pebble Bed React­or, ORNL/TM-9848 (also HTGR-85-161), Oak Ridge National Laboratory, Oak Ridge, Tenn., November 1985.

1984

C. O. Slater, Analysis of Phase I of the HTGR Bottom Reflector and Core Support Block Neutron-Streaming Experiment, ORNL/TM-9252, Oak Ridge National Laboratory, Oak Ridge, Tenn., July 1984.

C. O. Slater, "Analysis of Phase I of the ORNL HTGR Bottom Reflector and Support Block Neutron Streaming Experiment," Trans. Am. Nucl. Soc. 46, 637-638 (1984).

C. O. Slater and S. N. Cramer, "Analysis of Neutron Streaming in the HTGR Lower Support Regions," Proceedings of the Topical Meeting on Reactor Physics and Shielding 2, 724-735 (1984).

1982

L. S. Abbott, D. T. Ingersoll, F. J. Muckenthaler, and C. O. Slater, Review of ORNL-TSF Experiments for the Gas-Cooled Fast Breeder Reactor Program, ORNL-5805, Oak Ridge National Laboratory, Oak Ridge, Tenn., January 1982.

C. O. Slater and S. N. Cramer, Survey Analysis of Radiation Levels in the HTGR Lower Regions, ORNL/TM-8141, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 1982.

1981

C. O. Slater, D. A. Reed, S. N. Cramer, M. B. Emmett, and E. T. Tomlinson, Analysis of the Conceptual Shielding Design for the Upflow Gas-Cooled Fast Breeder Reactor, ORNL-5669, Oak Ridge Natioinal Laboratory, Oak Ridge, Tenn., January 1981.

C. O. Slater, S. N. Cramer, D. T. Ingersoll, M. L. Williams, F. J. Muckenthaler, J. J. Manning, and J. L. Hull, "Measurement and Calculation of the Effectiveness of the Gas-Cooled Fast Breeder Reactor Grid-Plate Shield," Nucl. Technol. 52, 354-369 (1981).

D. A. Reed, C. O. Slater, and H. L. Dodds, "Radial Shield Analysis of the Gas-Cooled Fast Reactor,"Trans. Am. Nucl. Soc. 38, 601-602 (1981).

1980

D. T. Ingersoll and C. O. Slater, DOGS—A Collection of Graphics for Support of Discrete Ordinates Codes, ORNL/TM-7188, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 1980.

C. O. Slater, E. T. Tomlinson, and L. R. Williams, Analysis of the Initial Shielding Design for the Upflow Gas-Cooled Fast Reactor (GCFR), ORNL/TM-7246, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 1980.

C. O. Slater and J. R. Knight, Analysis of the TSF GCFR Single-Cell Neutron Streaming Experiment, ORNL/GCR-80/16, Oak Ridge National Laboratory, Oak Ridge, Tenn., July 1980.

1979

C. O. Slater, S. N. Cramer, and D. T. Ingersoll, Analysis of the ORNL/TSF GCFR Grid-Plate Shield Design Confirmation Experi­ment, ORNL-5551, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 1979.

C. O. Slater, S. N. Cramer, and D. T. Ingersoll, "Analysis of the ORNL/TSF GCFR Grid-Plate Shield Design Confirmation Experi­ment," Trans. Am. Nucl. Soc. 32, 641-643 (1979).

1978

C. O. Slater, M. B. Emmett, and D. E. Bartine, "Final Analysis of a TSF Experiment on Neutron Streaming Through a Lattice of GCFR-Type Fuel Pins, ORNL/GCR-78/5, Oak Ridge National Laboratory, Oak Ridge, Tenn., 1978.

D. T. Ingersoll, C. O. Slater, and M. L. Williams, "Design of a Prototypic GCFR Grid-Plate Shield Design Confirmation Experiment," Trans. Am. Nucl. Soc. 28, 630-631 (1978).

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," Proceedings of the Fifth International Conference on Radiation Shielding, Science Press, Princeton, 1977.

D. E. Bartine, C. O. Slater, and L. R. Williams, "Application of an Advanced Shielding Analysis System to Gas-Cooled Fast Reactor Designs," Proceedings of the Fifth International Conference on Radiation Shielding, Science Press, Princeton, 1977.

1976

C. O. Slater and D. E. Bartine, Preliminary Analysis of a TSF Experiment on Neutron Streaming Through a Lattice of GCFR-Type Fuel Pins, ORNL/GCR-76/37, Oak Ridge National Laboratory, Oak Ridge, Tenn., November 1976.

C. O. Slater and D. E. Bartine, "Analysis of the GCFR Pin Streaming Experiment Performed at the TSF," Trans. Am. Nucl. Soc. 23, 624-625 (1976).

1975

C. O. Slater, MUSCAT-P: A Plane Geometry Version of the MUSCAT Computer Code, General Atomic Company Report GA-013289 (January 1975).

1974

C. O. Slater and J. C. Robinson, "Forward-Adjoint Coupling as a Means of Solving Three-Dimensional Deep-Penetration Problems," NSE 53, 332-337 (1974).

C. O. Slater, "A Monte Carlo Albedo Analysis of HTGR Radiation Streaming," Trans. Am. Nucl. Soc. 18, 397-398 (1974).

1973

C. O. Slater and J. C. Robinson, "Coupling of Forward and Adjoint Calculations to Solve Three-Dimensional Deep Penetration Problems", Ph.D. Thesis, The University of Tennessee, Knoxville, (March 1973). (Also Report Nos. BRL CR 100 and NEUT 0150-4).

C. O. Slater and J. C. Robinson, "Fortran Programs and Subpro­grams for the Implementation of the Three-Step Procedure and Two of Its Alternatives," BRL CR 99, Aberdeen Proving Ground, MD (March 1973). (Also Report No. NEUT 0150-5).

PRESENTATIONS

C. O. Slater, "TORT Problem Setup Requirements: Space Mesh, Geometry, Quadrature Sets, and Capability" and "TORT Problem Setup Requirements: Graphics Display of Flux/Response Data," presentations at the Deterministic Methods Seminar/TORT Workshop, Oak Ridge, Tenn., February 3-6, 1992.

D. T. Ingersoll, J. E. White, R. Q. Wright, H. T. Hunter, C. O. Slater, R. E. MacFarlane, and N. M. Greene, “Production and Testing of the VITAMIN-B6 and BUGLE-93 Neutron/Photon Cross-Section Libraries Derived From ENDF/B-VI Nuclear Data: The Abyss,” presented at the 8 th ASTM-EURATOM Symposium on Reactor Dosimetry, September 3, 1993.

J. E. White and C. O. Slater, “ORNL Experiences with FENDL-1.0 Nuclear Data,” The IAEA Advisory Group Meeting on the Completion of FENDL-1 and the Start of FENDL-2, Del Mar, CA, USA, December 5-9, 1995.

H. T. Hunter, R. W. Roussin, D. T. Ingersoll, C. O. Slater, E. Satori, and I. Kodeli, "SINBAD—An Electric Benchmark Database to Aid in the Simplification of Radiation Transport Computations," presentation at WATTEC, Knoxville, Tenn., February 19-22, 1996.

C. O. Slater, "Graphical Display of Flux and Response Data," presentation at the 1998 DORT/TORT Workshop, Nashville, Tenn., April 24-25, 1998.