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1980-85 Publications


1985

H. L. Adair, S. Raman, B. L. Broadhead, and R. L. Walker, "Availability and Use of Radiometric Neutron Monitor Materials for Characterizing Nuclear Reactor Environments," Nucl. Instrum. Methods Phys. Res. A236, 591-9 (1985).

M. B. Emmett, MORSE-CGA: A Monte Carlo Radiation Transport code With Array Geometry Capability, ORNL-6174, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1985.

R. E. Maerker, B. L. Broadhead, and J. J. Wagschal, "Theory of a New Unfolding Procedure in Pressurized Water Reactor Pressure Vessel Dosimetry and Development of an Associated Benchmark Data Base," Nucl. Sci. Eng. 91, 369-392 (1985).

L. M. Petrie, J. C. Turner, and G. B. Stewart, Review of PGDP Assessment of Criticality Safety Problems in Increasing Product Assay to 5 wt % U-235, ORNL/CSD/TM-225, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1985.

B. A. Worley and R. Q. Wright, An Automated Procedure for Calculating Time-Dependent Sensitivities in ORIGEN2, ORNL/TM-9771, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1985.

R. M. Westfall, J. R. Knight, P. B. Fox, O. W. Hermann, and J. C. Turner, TMI-2 Criticality Studies: Lower-Vessel Rubble and Analytical Benchmarking, ORNL/CSD/TM-222, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1985.

R. T. Santoro, J. M. Barnes, R. G. Alsmiller, Jr., M. B. Emmett, and J. D. Drischler, Comparisons of Calculated and Measured Spectral Distributions of Neutrons From a 14-MeV Neutron Source Inside the Tokamak Fusion Test Reactor, ORNL/TM-9888, Martin Marietta Energy Systems, Oak Ridge National Laboratory, December 1985.

C. V. Parks, O. W. Hermann, and J. R. Knight, "Radiation Dose Rates from Consolidated Fuel in Current-Generation Shipping Casks," 1985 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 10-14, 1985, Trans. Am. Nucl. Soc. 50, 129-131 (1985).

C. V. Parks, "Adjoint-Based Sensitivity Analysis for Reactor Accident Codes," 1985 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 10-14, 1985, Trans. Am. Nucl. Soc. 50, 283-285 (1985).

C. M. Hopper, "Economics of the Specification 6M Safety Re-Evaluation and Regulatory Requirements," 1985 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 10-14, 1985, Trans. Am. Nucl. Soc. 50, 311-313 (1985).

R. L. Childs and W. A. Rhoades, "The Extension of the Linear Nodal Method to Large Concrete Building Calculations," 1985 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 10-14, 1985, Trans. Am. Nucl. Soc. 50, 476-477 (1985).

W. A. Rhoades, R. L. Childs, D. T. Ingersoll, and F. J. Muckenthaler, "Analysis of the TORT Validation Experiment," 1985 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 10-14, 1985, Trans. Am. Nucl. Soc. 50, 473-475 (1985).

J. L. Thompson, W. A. Rhoades, M. B. Emmett, and H. L. Dodds, "A Method for Coupling Two-Dimensional to Three-Dimensional Discrete Ordinates Calculations," 1985 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 10-14, 1985, Trans. Am. Nucl. Soc. 50, 475-476 (1985).

L. J. Ott, C. F. Weber, and C. R. Hyman, "Station Blackout Calculations for Browns Ferry," Proc. 13th Water Reactor Safety Research Information Meeting, Gaithersburg, Md., October 22-25, 1985, NUREG/CP-0071, U. S. Nuclear Regulatory Commission, 1985.

F. G. Pin, B. A. Worley, E. M. Oblow, and R. Q. Wright, "Automated Sensitivity Analysis of the Radionuclide Migration Code UCB.NE-10.2," Proc. Int. Top. Meet. on High-Level Nuclear Waste Disposal Technology and Engineering, Pasco, Wash., September 24-26, 1985.

R. W. Barber, B. P. Brown, and C. M. Hopper, "Overview of DOE/ONS Criticality Safety Projects," Conf. Criticality Safety in the Storage of Fissile Material, Jackson, Wyo., September 9-11, 1985.

R. M. Westfall, "Criticality Analyses for TMI-2 Defueling," pp. 254-276 in Conf. Criticality Safety in the Storage of Fissile Material, Jackson, Wyo., September 9-11, 1985, CONF-850917-7.

C. V. Parks, O. W. Hermann, and J. R. Knight, Parametric Study of Radiation Dose Rates from Rail and Truck Spent Fuel Transport Casks, ORNL/CSD/TM-227, Lockheed Martin Energy Systems, Inc., Oak Ridge National Laboratory, August 1985.

C. F. Weber, R. P. Wichner, and S. A. Hodge, "Tellurium Precursor Effects on Iodine Transport in a BWR Accident," 1985 Annual Meeting of the American Nuclear Society, Boston, Mass., June 9-13, 1985, Trans. Am. Nucl. Soc. 49, 257-258 (1985).

R. E. Maerker, B. L. Broadhead, and M. L. Williams, "Application of LEPRICON Methodology to the Unfolding of Neutron Fluxes in the Arkansas Nuclear One-Unit 1 Reactor," 1985 Annual Meeting of the American Nuclear Society, Boston, Mass., June 9-13, 1985, Trans. Am. Nucl. Soc. 49, 425-426 (1985).

R. Q. Wright, "Resonance Interference Factor Fitting Procedure," 1985 Annual Meeting of the American Nuclear Society, Boston, Mass., June 9-13, 1985, Trans. Am. Nucl. Soc. 49, 418-420 (1985).

R. E. Maerker et al., "Combining Integral and Differential Dosimetry Data in an Unfolding Procedure with Application to the Arkansas Nuclear One-Unit 1 Reactor," Int. Conf. Nuclear Data for Basic and Applied Science, Santa Fe, N.Mex., May 13-17, 1985.

R. E. Maerker, M. L. Williams, B. L. Broadhead, J. J. Wagschal, and C. Y. Fu, "Revision and Expansion of the Data Base in the LEPRICON Dosimetry Methodology," EPRI NP-3841, Electric Power Research Institute, January 1985.

T. A. Gabriel and M. B. Emmett, "An Introduction to Combinatorial Geometry," LEP Experimenters' Workshop Shower Simulation, CERN, Geneva, Switzerland, January 29-31, 1985.

L. M. Petrie and J. T. Thomas, Assessment of Computational Performance in Nuclear Criticality, ORNL/CSD/TM-224, Martin Marietta Energy Systems, Oak Ridge National Laboratory, January 1985.

 

1984

B. L. Broadhead, N. B. Gove, and S. Raman, Preanalysis Calculations of the US/UK Joint Experiment in the Dounreay Prototype Fast Reactor, ORNL-6058, Oak Ridge National Laboratory, 1984.

J. G. Delene and O. W. Hermann, REFCO-83 User's Manual, NUREG/CR-3800, (ORNL/TM-9186), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1984.

M. B. Emmett, The MORSE Monte Carlo Radiation Transport Code System, ORNL-4972/R2, Oak Ridge National Laboratory, 1984.

O. W. Hermann and T. J. Burns, Impact of Containment Building Leakage on LWR Accident Risk, NUREG/CR-3539, ORNL/TM-8964, U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1984.

O. W. Hermann, C. F. Baes, C. W. Miller, C. L. Begovich, and A. L. Sjoreen, PRIMUS: A Computer Code for the Preparation of Radionuclide Ingrowth Matrices from User-Specified Sources, ORNL-5912, Oak Ridge National Laboratory, 1984.

R. P. Wichner et al., Noble Gas, Iodine, and Cesium Transport in a Postulated Loss of Decay Heat Removal Accident at Browns Ferry, NUREG/CR-3617 (ORNL/TM-9028), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1984.

C. F. Baes, R. D. Sharp, A. L. Sjoreen, and O. W. Hermann, TERRA: A Computer Code for Simulating the Transport of Environmentally Released Radionuclides Through Agriculture, ORNL-5785, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1984.

J. R. Knight and R. M. Westfall, "CESAR: A Criticality Experiment Storage and Retrieval Program," Sect. M12 of SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, Vols. I–III, NUREG/CR-0200 Rev. 3 (ORNL/NUREG/CSD-2/R3), December 1984.

R. M. Westfall, L. M. Petrie, N. M. Greene, and J. L. Lucius, "NITAWL-S: SCALE System Module for Performing Resonance Shielding and Working Library Production," Sect. F2 of SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, Vols. I–III, NUREG/CR-0200 Rev. 3 (ORNL/NUREG/CSD-2/R3), December 1984.

O. W. Hermann and R. M. Westfall, "ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms," Sect. F7 of SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, Vols. I–III, NUREG/CR-0200 Rev. 3 (ORNL/NUREG/CSD-2/R3), December 1984.

E. C. Beahm, R. P. Wichner, and C. F. Weber, "Chemical Factors Affecting Fission Product Transport in BWR Severe Accidents," Trans. of 12th Water Reactor Safety Research Information Meeting, Gaithersburg, Md., October 23, 1984.

H. L. Dodds, Jr. and R. M. Westfall, SKINATH - A Computer Program for Solving the Reactor Point Kinetics Equations with Simple Thermal-Hydraulic Feedback, ORNL/CSD/TM-210, Martin Marietta Energy Systems, Oak Ridge National Laboratory, September 1984.

H. L. Adair, S. Raman, B. L. Broadhead, and R. L. Walker, "Availability and Use of Radiometric Neutron Monitor Materials for Characterizing Nuclear Reactor Environments," Proc. Int. Nucl. Target Dev. Soc. 12th World Conf., Antwerp, Belgium, September 24-28, 1984.

R. E. Maerker, B. L. Broadhead, and M. L. Williams, "Recent Progress and Developments in LWR-PV Calculational Methodology," pp.639-648 in Proc. 5th Am. Soc. Test. Mater.-EURATOM Symp. Reactor Dosimetry 1, Germany, September 24-28, 1984.

B. L. Broadhead, D. G. Cacuci, and J. V. Pace, "Adjoint Transport Calculations for Sensitivity Analysis of the Hiroshima Air-Over-Ground Environment," 1984 Annual Meeting of the American Nuclear Society, New Orleans, La., June 3-7, 1984, Trans. Am. Nucl. Soc. 46, 638-40 (1984).

B. L. Broadhead and R. E. Maerker, "Sensitivities of the Flux Spectrum in the Cavity of a PWR to Variations in the Core Source Distribution," 1984 Annual Meeting of the American Nuclear Society, New Orleans, La., June 3-7, 1984, Trans. Am. Nucl. Soc. 46, 659-61 (1984).

B. L. Broadhead, A Nuclear Data Adjustment Methodology Utilizing Resonance Parameter Sensitivities and Uncertainties, ORNL/CSD/TM-212, Union Carbide Corp., Oak Ridge National Laboratory, January 1984.

1985

H. L. Adair, S. Raman, B. L. Broadhead, and R. L. Walker, "Availability and Use of Radiometric Neutron Monitor Materials for Characterizing Nuclear Reactor Environments," Nucl. Instrum. Methods Phys. Res. A236, 591-9 (1985).

M. B. Emmett, MORSE-CGA: A Monte Carlo Radiation Transport code With Array Geometry Capability, ORNL-6174, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1985.

R. E. Maerker, B. L. Broadhead, and J. J. Wagschal, "Theory of a New Unfolding Procedure in Pressurized Water Reactor Pressure Vessel Dosimetry and Development of an Associated Benchmark Data Base," Nucl. Sci. Eng. 91, 369-392 (1985).

L. M. Petrie, J. C. Turner, and G. B. Stewart, Review of PGDP Assessment of Criticality Safety Problems in Increasing Product Assay to 5 wt % U-235, ORNL/CSD/TM-225, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1985.

B. A. Worley and R. Q. Wright, An Automated Procedure for Calculating Time-Dependent Sensitivities in ORIGEN2, ORNL/TM-9771, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1985.

R. M. Westfall, J. R. Knight, P. B. Fox, O. W. Hermann, and J. C. Turner, TMI-2 Criticality Studies: Lower-Vessel Rubble and Analytical Benchmarking, ORNL/CSD/TM-222, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1985.

R. T. Santoro, J. M. Barnes, R. G. Alsmiller, Jr., M. B. Emmett, and J. D. Drischler, Comparisons of Calculated and Measured Spectral Distributions of Neutrons From a 14-MeV Neutron Source Inside the Tokamak Fusion Test Reactor, ORNL/TM-9888, Martin Marietta Energy Systems, Oak Ridge National Laboratory, December 1985.

C. V. Parks, O. W. Hermann, and J. R. Knight, "Radiation Dose Rates from Consolidated Fuel in Current-Generation Shipping Casks," 1985 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 10-14, 1985, Trans. Am. Nucl. Soc. 50, 129-131 (1985).

C. V. Parks, "Adjoint-Based Sensitivity Analysis for Reactor Accident Codes," 1985 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 10-14, 1985, Trans. Am. Nucl. Soc. 50, 283-285 (1985).

C. M. Hopper, "Economics of the Specification 6M Safety Re-Evaluation and Regulatory Requirements," 1985 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 10-14, 1985, Trans. Am. Nucl. Soc. 50, 311-313 (1985).

R. L. Childs and W. A. Rhoades, "The Extension of the Linear Nodal Method to Large Concrete Building Calculations," 1985 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 10-14, 1985, Trans. Am. Nucl. Soc. 50, 476-477 (1985).

W. A. Rhoades, R. L. Childs, D. T. Ingersoll, and F. J. Muckenthaler, "Analysis of the TORT Validation Experiment," 1985 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 10-14, 1985, Trans. Am. Nucl. Soc. 50, 473-475 (1985).

J. L. Thompson, W. A. Rhoades, M. B. Emmett, and H. L. Dodds, "A Method for Coupling Two-Dimensional to Three-Dimensional Discrete Ordinates Calculations," 1985 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 10-14, 1985, Trans. Am. Nucl. Soc. 50, 475-476 (1985).

L. J. Ott, C. F. Weber, and C. R. Hyman, "Station Blackout Calculations for Browns Ferry," Proc. 13th Water Reactor Safety Research Information Meeting, Gaithersburg, Md., October 22-25, 1985, NUREG/CP-0071, U. S. Nuclear Regulatory Commission, 1985.

F. G. Pin, B. A. Worley, E. M. Oblow, and R. Q. Wright, "Automated Sensitivity Analysis of the Radionuclide Migration Code UCB.NE-10.2," Proc. Int. Top. Meet. on High-Level Nuclear Waste Disposal Technology and Engineering, Pasco, Wash., September 24-26, 1985.

R. W. Barber, B. P. Brown, and C. M. Hopper, "Overview of DOE/ONS Criticality Safety Projects," Conf. Criticality Safety in the Storage of Fissile Material, Jackson, Wyo., September 9-11, 1985.

R. M. Westfall, "Criticality Analyses for TMI-2 Defueling," pp. 254-276 in Conf. Criticality Safety in the Storage of Fissile Material, Jackson, Wyo., September 9-11, 1985, CONF-850917-7.

C. V. Parks, O. W. Hermann, and J. R. Knight, Parametric Study of Radiation Dose Rates from Rail and Truck Spent Fuel Transport Casks, ORNL/CSD/TM-227, Lockheed Martin Energy Systems, Inc., Oak Ridge National Laboratory, August 1985.

C. F. Weber, R. P. Wichner, and S. A. Hodge, "Tellurium Precursor Effects on Iodine Transport in a BWR Accident," 1985 Annual Meeting of the American Nuclear Society, Boston, Mass., June 9-13, 1985, Trans. Am. Nucl. Soc. 49, 257-258 (1985).

R. E. Maerker, B. L. Broadhead, and M. L. Williams, "Application of LEPRICON Methodology to the Unfolding of Neutron Fluxes in the Arkansas Nuclear One-Unit 1 Reactor," 1985 Annual Meeting of the American Nuclear Society, Boston, Mass., June 9-13, 1985, Trans. Am. Nucl. Soc. 49, 425-426 (1985).

R. Q. Wright, "Resonance Interference Factor Fitting Procedure," 1985 Annual Meeting of the American Nuclear Society, Boston, Mass., June 9-13, 1985, Trans. Am. Nucl. Soc. 49, 418-420 (1985).

R. E. Maerker et al., "Combining Integral and Differential Dosimetry Data in an Unfolding Procedure with Application to the Arkansas Nuclear One-Unit 1 Reactor," Int. Conf. Nuclear Data for Basic and Applied Science, Santa Fe, N.Mex., May 13-17, 1985.

R. E. Maerker, M. L. Williams, B. L. Broadhead, J. J. Wagschal, and C. Y. Fu, "Revision and Expansion of the Data Base in the LEPRICON Dosimetry Methodology," EPRI NP-3841, Electric Power Research Institute, January 1985.

T. A. Gabriel and M. B. Emmett, "An Introduction to Combinatorial Geometry," LEP Experimenters' Workshop Shower Simulation, CERN, Geneva, Switzerland, January 29-31, 1985.

L. M. Petrie and J. T. Thomas, Assessment of Computational Performance in Nuclear Criticality, ORNL/CSD/TM-224, Martin Marietta Energy Systems, Oak Ridge National Laboratory, January 1985.

  

1983

J. A. Bucholz et al., "Standard Composition Library," Sect. M8 of SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation - Volume 3: Miscellaneous, ORNL/NUREG/CSD-2/V3/R1, U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1983.

M. B. Emmett, The MORSE Monte Carlo Radiation Transport Code System, ORNL-4972/R1, Union Carbide Corp., Oak Ridge National Laboratory, 1983.

C. W. Forsberg, C. W. Alexander, G. W. Morrison, and O. W. Hermann, Integrated Data Base Program: An Overview of Data Handling and Projection Modeling, ORNL/NFW-83/8, Union Carbide Corp., Oak Ridge National Laboratory, 1983.

C. W. Miller, C. L. Begovich, and O. W. Hermann, "ANEMOS: A Code to Estimate Radionuclide Air Concentrations and Ground Deposition Rates," Health Phys., 45, 209-210 (1983).

W. D. Turner and O. W. Hermann, SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation - Volume 1: Control Modules, ORNL/NUREG/CSD-2/V1/R2, U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1983.

J. J. Wagschal, R. E. Maerker, and B. L. Broadhead, "Uncertainty Analysis of Benchmark Dosimetry Measurements," Nucl. Data for Sci. and Technol. 436-440 (1983).

R. M. Westfall and J. R. Knight, Radiation Levels in a Gaseous Diffusion Plant Assuming a Low-Enriched Criticality Event Corresponding to the Ansi-Standard Minimum Accident of Concern, ORNL/CSD/INF-82/7, Union Carbide Corp. (Nuclear Division), Oak Ridge National Laboratory, 1983.

R. P. Wichner et al., SBLOCA Outside Containment at Browns Ferry Unit One, Volume 2. Iodine, Cesium, and Noble Gas Distribution and Release, NUREG/CR-2672, Vol. 2 (ORNL/TM-8119/V2), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1983.

B. L. Broadhead and H. L. Dodds, "Sensitivity Coefficients of Self-Shielded Cross Sections to the Resonance Parameters," 1983 Winter Meeting of the American Nuclear Society, San Francisco, Calif., October 30-November 3, 1983, Trans. Am. Nucl. Soc. 45, 703-4 (1983).

C. F. Weber et al., "Fission Product Transport in a BWR Small-Break LOCA," 1983 Winter Meeting of the American Nuclear Society, San Francisco, Calif., October 30-November 3, 1983, Trans. Am. Nucl. Soc. 45, 479-480 (1983).

C. V. Parks, Calculation of Radiation Fields and Monkey Mid-Head and Mid-Thorax Responses in AFRRI-TRIGA Reactor Facility Experiments, ORNL/TM-8807, Union Carbide Corp., Oak Ridge National Laboratory, July 1983.

O. W. Hermann and C. W. Alexander, "Spent Fuel Photon and Neutron Source Spectra," 1983 Annual Meeting of the American Nuclear Society, Detroit, MI, June 12-16, 1983, Trans. Am. Nucl. Soc. 44, 474-5 (1983).

R. M. Westfall, "Benchmark Solutions for the Infinite Critical Cylinder," 1983 Annual Meeting of the American Nuclear Society, Detroit, MI, June 12-16, 1983, Trans. Am. Nucl. Soc. 44, 281-283 (1983).

T. A. Gabriel, R. A. Lillie, and R. L. Childs, The Use of Gd-Loaded Scintillation Detector Systems for Inverse Beta Decay Reactions, ORNL/TM-8711, Union Carbide Corp., Oak Ridge National Laboratory, May 1983.

C. V. Parks et al., "Standardized Analyses of Nuclear Shipping Containers," Proc. 7th Inter. Symp. on Packaging and Transportation of Radioactive Materials, New Orleans, La., May 15-20, 1983, Vol II, p. 1455 of CONF-830528, 479-80 (1983).

T. A. Gabriel et al., Neutron and Gamma-Ray Shielding Requirements for a Below-Ground Neutrino Detector System at the Rutherford Laboratory Spallation Neutron Source, ORNL/TM-8355, Union Carbide Corp., Oak Ridge National Laboratory, March 1983.

R. M. Westfall, "Computational Benchmark Problem Committee -- Present Activities and New Problem Areas," pp. 194 in Conf. Advances in Reactor Computations, Salt Lake City, Utah, March 28-31, 1983, ISBN: 0-89448-117, 7.

D. G. Cacuci, P. J. Maudlin, and C. V. Parks, "Adjoint Sensitivity analysis of Extremum-Type Responses in Reactor Safety," Nucl. Sci. Eng. 83, 112-135, January 1983.

W. E. Ford III et al., "The CSRL-V ENDF/B-V 227-Group Neutron Cross-Section Library and Its Application to Thermal Reactor and Criticality Safety Benchmarks," Proc. Thermal Reactor Benchmark Calculations, Techniques, Results, and Applications, Electric Power Research Institute, Upton, N.Y., May 17-18, 1982, EPRI NP-2855, pp. 19-1 - 19-25, 1983.

 

1982

R. P. Wichner et al., Station Blackout at Browns Ferry Unit One - Iodine and Noble Gas Distribution and Release, NUREG/CR-2182, Vol. 2, U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1982.

M. B. Emmett and W. A. Rhoades, A Short Course in the Operation of Interact, ORNL/CSD/TM-187, Union Carbide Corp., Oak Ridge National Laboratory, 1982.

T. J. Hoffman and J. S. Tang, XSDRNPM-S Biasing of MORSE-SGC/S Shipping Cask Calculations, NUREG/CR-2342 (ORNL/CSD/TM-175), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, October 1982.

W. A. Rhoades and M. B. Emmett, DOS: The Discrete Ordinates System, ORNL/TM-8362, Union Carbide Corp., Oak Ridge National Laboratory, September 1982.

J. C. Ryman, O. W. Hermann, C. C. Webster, and C. V. Parks, Fuel Inventory and Afterheat Power Studies of Uranium-Fueled Pressurized Water Reactor Fuel Assemblies Using the SAS2 and ORIGEN-S Module of SCALE with an ENDF/B-V Updated Cross Section Library, NUREG/CR-2397 (ORNL/CSD-90), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, September 1982.

J. S. Tang and B. A. Worley, Monte Carlo Calculations of Control-Rod Worth of a Medium-Size Pebble-Bed Reactor, ORNL/TM-8111, Union Carbide Corp., Oak Ridge National Laboratory, September 1982.

J. C. Ryman, O. W. Hermann, C. C. Webster, and C. V. Parks, "A Simplified Method for Predicting Afterheat Power From Uranium-Fueled PWR Fuel Assemblies," Proc. Inter. Mtg. on Thermal Nucl. Reactor Safety, Chicago, Ill., August 29-September 2, 1982.

C. V. Parks, Ed., SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, Vols. 1-3 NUREG/CR-0200, U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, (originally issued July 1980, reissued January 1982, Rev. 1 issued July 1982, Rev. 2 issued June 1983, Rev. 3 issued 12/84).

W. E. Ford III, B. R. Diggs, L. M. Petrie, C. C. Webster, and R. M. Westfall, CSRL-V: Processed ENDF/B-V 227-Neutron-Group and Pointwise Cross-Section Libraries for Criticality Safety, Reactor and Shielding Studies, NUREG/CR-2306 (ORNL/CSD/TM-160), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, June 1982.

T. J. Hoffman, J. S. Tang, C. V. Parks, and R. L. Childs, "An Automated Biasing Approach to Monte Carlo Shipping Cask Calculations," 1982 Annual Meeting of the American Nuclear Society, Los Angeles, Calif., June 6-10, 1982, Trans. Am. Nucl. Soc. 41, 491-492 (1982).

J. P. Renier, J. R. Knight, and R. M. Westfall, "Dose Levels and Neutron Reaction Rates for HPRR and SHEBA," 1982 Annual Meeting of the American Nuclear Society, Los Angeles, Calif., June 6-10, 1982, Trans. Am. Nucl. Soc. 41, 502-504 (1982).

D. G. Cacuci, P. J. Maudlin, and C. V. Parks, Applications of Differential Sensitivity Theory for Extremum-Type Responses, ORNL/TM-7717, Union Carbide Corp., Oak Ridge National Laboratory, May 1982.

M. Yamauchi, M. B. Emmett, R. T. Santoro, H. Iida, Y. Seki, and H. Narita, Toroidal Geometry Subroutines for MORSE-CG, ORNL/TM-8244, Union Carbide Corp., Oak Ridge National Laboratory, April 1982.

J. M. Ryskamp et al., "Sensitivity and Uncertainty Analysis of the Coupled Fast Reactivity Measurements Facility Central Flux Spectrum," Nucl. Technol. 57, 20-35, April 1982.

J. J. Wagschal, R. E. Maerker, and B. L. Broadhead, "Surveillance Dosimetry: Achievements and Disappointments," pp. 79-92 in Proc. of 4th Am. Soc. Test. Mater./EURATOM Symp. Reactor Dosimetry 1, March 21-26, 1982.

 

1981

C. V. Parks and P. J. Maudlin, "Application of Differential Sensitivity Theory to a Neutronic/Thermal- Hydraulic Reactor Safety Code," Nucl. Tech. 54, 38-53 (1981); also ORNL/CSD/TM-154.

J. D. Smith, III and B. L. Broadhead, Multigroup Covariance Matrices for Fast Reactor Studies, ORNL/TM-7389, Union Carbide Corp., Oak Ridge National Laboratory, 1981.

C. F. Weber, "Analysis and Solution of the Ill-Posed Inverse Heat Conduction Problem," Int. J. Heat Mass Transfer, 24, 1783-1792 (1981).

R. M. Westfall, "Critical Masses for the Even-Neutron-Numbered Transuranium Actinides," Nucl. Sci. Eng., 79(2), 237-239 (1981).

R. E. Maerker, J. J. Wagschal, and B. L. Broadhead, "Development and Demonstration of an Advanced Methodology for LWR Dosimetry Applications," EPRI NP-2188, Electric Power Research Institute, Research Project 1399-1; Interim Report, December 1981.

C. V. Parks and P. J. Maudlin, "Technical Note: An Adjoint-Based Sensitivity Methodology for Reactor Safety," Nucl. Safety, 22(6), 725-727, November-December 1981.

J. J. Wagschal and B. L. Broadhead, "Evaluation of the New ISNF One-Dimensional Model," 1981 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 29-December 3, 1981, Trans. Am. Nucl. Soc. 39, 887-889 (1981).

C. F. Weber, "Application of an Inverse Heat Conduction Solution Procedure," 1981 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 29-December 3, 1981, Trans. Am. Nucl. Soc., 39, 496-497 (1981).

B. L. Broadhead and H. L. Dodds, Jr., "Treatment of Energy Self-Shielding (f-factors) in Data Adjustments for Fast Reactors," 1981 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 29-December 3, 1981, Trans. Am. Nucl. Soc., 39, 929-930 (1981).

B. D. Ganapol and R. M. Westfall, "Neutron Transport Problems Having Analytical Solutions," 1981 Winter Meeting of the American Nuclear Society, San Francisco, Calif., November 29-December 3, 1981, Trans. Am. Nucl. Soc., 39, 482-484 (1981).

S. M. Bowman, The Development of Depletion Perturbation Theory for a Reactor Nodal Code, ORNL/TM-7589, Union Carbide Corp., Oak Ridge National Laboratory, September 1981.

P. J. Maudlin, C. V. Parks, and D. G. Cacuci, "Differential Sensitivity Theory Applied to Movement of Maxima Responses," 1981 Annual Meeting of the American Nuclear Society, Miami, Fla., June 7-11, 1981, Trans. Am. Nucl. Soc., 38, 333 (1981).

C. W. Miller and O. W. Hermann, "ANEMOS: A Code to Calculate Radionuclide Concentrations in Air," 1981 Annual Meeting of the American Nuclear Society, Miami, Fla., June 7-11, 1981, Trans. Am. Nucl. Soc., 38, 97-98 (1981).

A. M. Hathout, R. M. Westfall, and H. L. Dodds, Validation of Three Cross-Section Libraries Used with the SCALE System for Criticality Safety Analysis, NUREG/CR-1917 (ORNL/NUREG/CSD/TM-19), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, June 1981.

M. B. Emmett, DOMINO-II, A General Purpose Code for Coupling DOT-IV Discrete Ordinates and Monte Carlo Radiation Transport Calculations, ORNL/TM-7771, Union Carbide Corp., Oak Ridge National Laboratory, May 1981.

W. A. Rhoades, M. B. Emmett, J. R. Knight, and W. W. Engle, Radiation Analysis of the Conceptual Design Study 1000-MW9E0 Loop-Design LMFBR, ORNL/TM-7492, Union Carbide Corp., Oak Ridge National Laboratory, May 1981.

D. G. Cacuci, P. J. Maudlin, C. V. Parks, and C. F. Weber, "Recent Advances and Applications of Differential Sensitivity Theory in Reactor Safety," Vol. II, p. 237 in Proc. Inter. Topical Mtg. on Advances in Mathematical Methods for the Solution of Nuclear Engineering Problems, Munich, Germany, April 27-29, 1981.

 

1980

G. E. Whitesides and R. M. Westfall, Quarterly Report on Program for the Standardized Analysis of Fuel Shipping Containers, ORNL/CSD/INF-80/4, Union Carbide Corp. (Nuclear Division), Oak Ridge National Laboratory, 1980.

D. G. Cacuci, C. F. Weber, E. M. Oblow, and J. H. Marable, "Sensitivity Theory for General Systems of Nonlinear Equations," Nucl. Sci. Eng. 75, 88-110 (1980).

P. J. Maudlin, C. V. Parks, and C. F. Weber, "Thermal-Hydraulic Differential Sensitivity Theory," Paper No. 80-WA/HT-56 in Proc. of the ASME Winter Annual Meeting, Chicago, Ill., November 16-21, 1980; also ORNL/CSD/TM-126.

A. M. Hathout, R. M. Westfall, and H. L. Dodds, "SCALE System Cross-Section Validation for Criticality Safety Analysis," 1980 Winter Meeting of the American Nuclear Society: International Conference on World Nuclear Energy - Accomplishments and Perspectives, Washington, D. C., November 16-21, 1980, Trans. Am. Nucl. Soc. 35, 281-3 (1980).

C. V. Parks, P. J. Maudlin, and C. F. Weber, "Application of Differential Sensitivity Theory to Transients with Scram," 1980 Winter Meeting of the American Nuclear Society: International Conference on World Nuclear Energy - Accomplishments and Perspectives, Washington, D. C., November 16-21, 1980, Trans. Am. Nucl. Soc. 35, 376-378 (1980).

J. M. Ryskamp et al., "Sensitivity and A Priori Uncertainty Analysis of the CFRMF Central Flux Spectrum," 1980 Winter Meeting of the American Nuclear Society: International Conference on World Nuclear Energy - Accomplishments and Perspectives, Washington, D. C., November 16-21, 1980, Trans. Am. Nucl. Soc. 35, 556-557 (1980).

B. L. Broadhead and J. J. Wagschal, "The ISNF: A New CSEWG Dosimetry Benchmark (Computational Problems and Their Solution)," 1980 Winter Meeting of the American Nuclear Society: International Conference on World Nuclear Energy - Accomplishments and Perspectives, Washington, D. C., November 16-21, 1980, Trans. Am. Nucl. Soc. 35, 466-8 (1980).

J. T. West, R. M. Westfall, G. E. Whitesides, and J. T. Thomas, "TMI-2 Criticality Analysis - Analytical Models and Methods," 1980 Winter Meeting of the American Nuclear Society: International Conference on World Nuclear Energy - Accomplishments and Perspectives, Washington, D. C., November 16-21, 1980, Trans. Am. Nucl. Soc. 35, 274-6 (1980).

R. M. Westfall, J. T. West, G. E. Whitesides, and J. T. Thomas, "TMI-2 Criticality Analysis - Parametric Studies and Overall Results," 1980 Winter Meeting of the American Nuclear Society: International Conference on World Nuclear Energy - Accomplishments and Perspectives, Washington, D. C., November 16-21, 1980, Trans. Am. Nucl. Soc. 35, 276-7 (1980).

C. F. Weber, "Analysis and Solution of an Inverse Heat Conduction Problem," in Proc. of the Fall Meeting of the Society for Industrial and Applied Mathematics, Houston, Tex., November 6-8, 1980.

R. L. Childs, Generalized Perturbation Theory Using Two-Dimensional, Discrete Ordinates Transport Theory, ORNL/CSD/TM-127, Union Carbide Corp., Oak Ridge National Laboratory, June 1980.

S. M. Bowman, M. L. Williams, and H. L. Dodds, "Implementation of Generalized Perturbation Theory into the 3-D Nodal Code SIMULATE," 1980 Annual Meeting of the American Nuclear Society, Las Vegas, Nev., June 9-12, 1980, Trans. Am. Nucl. Soc., 34, 305-7 (1980).

W. E. Ford, III, R. M. Westfall, B. R. Diggs, C. C. Webster, and J. R. Knight, "CSRL-V: An ENDF/B-V 227-Group Cross-Section Library for Criticality Safety Studies," 1980 Annual Meeting of the American Nuclear Society, Las Vegas, Nev., June 9-12, 1980, Trans. Am. Nucl. Soc., 34, 331-3 (1980).

P. J. Maudlin and C. V. Parks, "Generalized Sensitivity Theory Applied to the MELT-IIIA Fast Reactor Safety Code," 1980 Annual Meeting of the American Nuclear Society, Las Vegas, Nev., June 9-12, 1980, Trans. Am. Nucl. Soc., 34, 520-521, 1980.

C. F. Weber, D. G. Cacuci, and C. V. Parks, "Applications of Differential Sensitivity Theory for Problems with Discontinuities," 1980 Annual Meeting of the American Nuclear Society, Las Vegas, Nev., June 9-12, 1980, Trans. Am. Nucl. Soc., 34, 314-315, 1980.

E. T. Tomlinson, R. L. Childs, and R. A. Lillie, DOS Perturbation Modules DGRAD/VIP/TPERT, ORNL/CSD/TM-116, Union Carbide Corp., Oak Ridge National Laboratory, May 1980.

D. G. Cacuci, C. F. Weber, E. M. Oblow, and J. H. Marable, Generalized Sensitivity Theory for Systems of Coupled Nonlinear Equations, NUREG/CR-1003 (ORNL/NUREG/TM-349), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, January 1980.

 

 

 

 

 

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