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1990-95 Publications


1995

E. C. Beahm et al., Sludge Washing and Dissolution of ORNL Melton Valley Storage Tank (MVST) Waste: Third Interim Letter Report, ORNL/M-4022, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1995.

E. C. Beahm et al., Washing and Dissolution of Actinides from Melton Valley Storage Tank (MVST) Waste: Interim Letter Report, ORNL/M-4081, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1995.

C. M. Hopper, "Elements of a Nuclear Criticality Safety Program," Nucl. Safety 36(2), 234-242 (1995).

R. M. Westfall, The 1993 and 1994 Annual Criticality Review Committee Appraisals, ORNL/CF-95/59, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1995.

M. J. Haire and W. C. Jordan, Relative Risk of Nuclear Criticality Occurring from Low-Enriched Uranium and High-Enriched Uranium Deposits at the K-25 Site, Oak Ridge, Tennessee, K/ER-215, Lockheed Martin Energy Systems, Inc., Oak Ridge K-25 Site, December 1995.

C. V. Parks and B. L. Broadhead, "Review of Criticality Safety and Shielding Analysis Issues for Transportation Packages," PATRAM'95, Las Vegas, Nev., December 3-8, 1995.

Y. Y. Liu and J. S. Tang, "Analysis of Radiation Measurement Data of the BUSS Cask," PATRAM'95, Las Vegas, Nev., December 3-8, 1995.

C. W. Forsberg et al., DUSCOBS - A Depleted-Uranium Silicate Backfill for Transport, Storage and Disposal of Spent Nuclear Fuel, ORNL/TM-13045, Martin Marietta Energy Systems, Oak Ridge National Laboratory, November 1995.

M. D. DeHart and S. M. Bowman, Analysis of Fresh Fuel Critical Experiments Appropriate for Burnup Credit Validation, ORNL/TM-12959, Lockheed Martin Energy Systems, Inc., Oak Ridge National Laboratory, October 1995.

B. Basoglu et al., "Evaluation of Several Parallel Algorithms for KENO V.a," 1995 Winter Meeting American Nuclear Society, San Francisco, Calif., October 29-November 2, 1995, Trans. Am. Nucl. Soc. 73, 183-184 (1995).

S. M. Bowman and B. L. Broadhead, "Dose Rates in the ABWR Upper Drywell for a Dropped Fuel Bundle Accident," 1995 Winter Meeting American Nuclear Society, San Francisco, Calif., October 29-November 2, 1995, Trans. Am. Nucl. Soc. 73, 364-366 (1995).

M. D. DeHart, O. W. Hermann, and C. V. Parks, "Validation of SCALE Depletion Methods for PWR Spent Fuel Isotopic Characterization," 1995 Winter Meeting American Nuclear Society, San Francisco, Calif., October 29-November 2, 1995, Trans. Am. Nucl. Soc. 73, 361-363 (1995).

J. S. Tang and B. L. Broadhead, "Applications of SAS4 Monte Carlo Shielding Sequence to Deep- Penetration Problems," 1995 Winter Meeting American Nuclear Society, San Francisco, Calif., October 29-November 2, 1995, Trans. Am. Nucl. Soc. 73, 363-364 (1995).

B. L. Broadhead and C. V. Parks, "Overview of SCALE System Shielding Capabilities," 1995 Winter Meeting American Nuclear Society, San Francisco, Calif., October 29-November 2, 1995, Trans. Am. Nucl. Soc. 73, 360-361 (1995).

C. M. Hopper, W. C. Jordan, and D. F. Hollenbach, "Calculated Neutron Spectra for Heterogeneous U(93) and CH2 Critical Assemblies," 1995 Winter Meeting American Nuclear Society, San Francisco, Calif., October 29-November 2, 1995, Trans. Am. Nucl. Soc. 73, 220-222 (1995).

M. L. Williams, M. Asgari, and R. Q. Wright, "ENDF/B-VI Performance for Thermal Reactor Analysis," 1995 Winter Meeting American Nuclear Society, San Francisco, Calif., October 29-November 2, 1995, Trans. Am. Nucl. Soc. 73, 420-22 (1995).

C. V. Parks, W. C. Jordan, L. M. Petrie, and R. Q. Wright, "Use of Metal/Uranium Mixtures to Explore Data Uncertainties," 1995 Winter Meeting American Nuclear Society, San Francisco, Calif., October 29-November 2, 1995, Trans. Am. Nucl. Soc. 73, 217-218 (1995).

E. C. Beahm et al., "Washing and Dissolution of Melton Valley Storage Tank Sludge at Oak Ridge National Laboratory," 9th Symposium on Separation Science and Technology for Energy Applications, Gatlinburg, Tenn., October 22-26, 1995.

M. D. DeHart and C. V. Parks, "Issues Related to Criticality Safety Analysis for Burnup Credit Applications," ICNC'95, Fifth International Conference on Nuclear Criticality Safety, Albuquerque, N. Mex., September 17-21, 1995.

M. D. DeHart, O. W. Hermann, and C. V. Parks, "Validation of a Method for Prediction of Isotopic Concentrations in Burnup Credit Applications," ICNC'95, Fifth International Conference on Nuclear Criticality Safety, Albuquerque, N. Mex., September 17-21, 1995.

L. C. Leal, R. M. Westfall, W. C. Jordan, and R. Q. Wright, "Nuclear Data Needs for Application in Nuclear Criticality Safety Programs," Proc. of the Fifth International Conference on Nuclear Criticality Safety, ICNC’95, Albuquerque, N. Mex., September 17-21, 1995.

D. F. Hollenbach, S. M. Bowman, L. M. Petrie, and C. V. Parks, "New Enhancements to SCALE for Criticality Safety Analysis," ICNC'95, Fifth International Conference on Nuclear Criticality Safety, Albuquerque, N. Mex., September 17-21, 1995.

S. M. Bowman, R. Q. Wright, M. D. DeHart, and C. V. Parks, "Recent Validation Experience with Multigroup Cross-Section Libraries and SCALE at ORNL," ICNC'95, Fifth International Conference on Nuclear Criticality Safety, Albuquerque, N. Mex., September 17-21, 1995.

B. L. Broadhead, R. L. Childs, and C. M. Hopper, "Verification of Criticality Accident Alarm System for Environmental Restoration Activities," ICNC'95, Fifth International Conference on Nuclear Criticality Safety, Albuquerque, N. Mex., September 17-21, 1995.

R. Q. Wright and W. C. Jordan, "ENDF/B-VI Chlorine Evaluation is Deficient," ICNC'95, Fifth International Conference on Nuclear Criticality Safety, Albuquerque, N. Mex., September 17-21, 1995.

S. Raman and B. D. Murphy, "US/UK Actinides Experiment at the Dounreay PFR, I. Fission Products," Global 95 International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems, Versailles, France, September 11-14, 1995.

C. V. Parks, R. Q. Wright, and W. C. Jordan, Adequacy of the 123-Group Cross-Section Library for Criticality Analyses of Water-Moderated Uranium Systems NUREG/CR-6328 (ORNL/TM-12970), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, August 1995.

R. Q. Wright, J. P. Renier, and J. A. Bucholz, ANSL-V: ENDF/B-V Based Multigroup Cross-Section Libraries for Advanced Neutron Source Reactor Studies, Supplement 1, ORNL-6618/s1, Lockheed Martin Energy Systems, Inc., Oak Ridge National Laboratory, August 1995.

S. Raman et al., Dounreay PFR Irradiation History for the Joint US/UK Actinide Sample Exposures, ORNL/TM-12984, Martin Marietta Energy Systems, Oak Ridge National Laboratory, July 1995.

S. M. Bowman, C. V. Parks, and S. K. Martin, "Maintaining SCALE as a Reliable Computational System for Criticality Safety Analysis," 1995 Annual Meeting American Nuclear Society, Philadelphia, Pa., June 25-29, 2005, Trans. Am. Nucl. Soc. 72, 198-199 (1995).

B. L. Broadhead and C. M. Hopper, "Updated Tool for Nuclear Criticality Accident Emergency Response," 1995 Annual Meeting American Nuclear Society, Philadelphia, Pa., June 25-29, 2005, Trans. Am. Nucl. Soc. 72, 218-220 (1995).

C. M. Hopper, "Criticality Safety Considerations for Low-Level-Waste Facilities," 1995 Annual Meeting American Nuclear Society, Philadelphia, Pa., June 25-29, 2005, Trans. Am. Nucl. Soc. 72, 184-85, (1995).

B. L. Broadhead et al., Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel, ORNL/TM-12742, Lockheed Martin Energy Systems, Inc., Oak Ridge National Laboratory, June 1995.

E. C. Beahm, C. F. Weber, J. L. Collins, B. Z. Egan, and C. W. Chase, "Washing and Dissolution of Melton Valley Storage Tank Sludge at Oak Ridge National Laboratory," 2nd International Conference on Waste Management, Washington, D.C., May 17-19, 1995.

L. C. Leal, W. C. Jordan, and R. Q. Wright, "Nuclear Data for Criticality Safety - Current Issues," Proc. Nuclear Criticality Technology and Safety Project Embedded Topical Meeting, San Diego, Calif., May 17, 1995.

D. F. Hollenbach and L. M. Petrie, "Assurances Associated with Monte Carlo Code Results," Proc. Nuclear Criticality Technology and Safety Project Embedded Topical Meeting, San Diego, Calif., May 17, 1995.

B. L. Broadhead, J. S. Tang, R. L. Childs, C. V. Parks, and H. Taniuchi, "Evaluation of Shielding Analysis Methods in Spent Fuel Cask Environments," EPRI TR-104329, Electric Power Research Institute, May 1995.

L. C. Leal, O. W. Hermann, and C. V. Parks, "ARP: A PC-Compatible Scheme for Generating ORIGEN-S Cross- Section Library," Proc. Sixth Annual Inter. Conf. on High-Level Waste Management, Las Vegas, Nev., April 30 - May 5, 1995.

L. C. Leal, O. W. Hermann, and C. V. Parks, "Automatic Rapid Processing Cross-Section Libraries for the Prediction of PWR Spent Fuel Isotopic Compositions," Proc. of Inter. Conf. on Math. and Comp., Reactor Physics, and Environmental Analyses, Portland, Oreg., April 30 - May 4, 1995,.

S. M. Bowman, M. D. DeHart, and C. V. Parks, "Validation of SCALE-4 for Burnup Credit Applications," Nucl. Tech. 110, 53 (1995).

B. L. Broadhead, "Feasibility Assessment of Burnup Credit in the Criticality Analysis of Shipping Casks with Boiling Water Reactor Spent Fuel," Nucl. Tech. 110, 1-21 (1995).

M. D. DeHart, SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 4 - Three Mile Island Unit 1 Cycle 5, ORNL/TM-12294/V4, Martin Marietta Energy Systems, Oak Ridge National Laboratory, March 1995.

S. M. Bowman and O. W. Hermann, SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 3 - Surry Unit 1 Cycle 2, ORNL/TM-12294/V3, Martin Marietta Energy Systems, Oak Ridge National Laboratory, March 1995.

S. M. Bowman, O. W. Hermann, and M. C. Brady, SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 2 - Sequoyah Unit 2 Cycle 3, ORNL/TM-12294/V2, Martin Marietta Energy Systems, Oak Ridge National Laboratory, March 1995.

M. D. DeHart, SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 1 - Summary, ORNL/TM-12294/V1, Martin Marietta Energy Systems, Oak Ridge National Laboratory, March 1995.

C. M. Hopper, R. H. Odegaarden, C. V. Parks, and P. B. Fox, Criticality Safety Criteria for License Review of Low-Level Waste Facilities, NUREG/CR-6284 (ORNL/TM-12845), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, March 1995.

E. C. Beahm, C. F. Weber, J. L. Collins, B. Z. Egan, and C. W. Chase, "Washing and Dissolution of Melton Valley Storage Tank Sludge at Oak Ridge National Laboratory," Efficient Separations and Processing Integrated Program Technical Integration and Exchange Meeting, Washington, D.C.January 24-26, 1995.

 

1994

C. M. Hopper, "Department of Energy Plutonium ES&H Vulnerability Assessment Oak Ridge Site Assessment Team Report."

B. Basoglu et al., "Simulation of Hypothetical Criticality Accidents Involving Homogeneous Damp Low-Enriched UO2 Powder Systems," Nucl. Technol. 105, 14 (1994).

C. F. Haught et al., "Criticality Safety Analysis of a Calciner Exit Chute," Nucl. Technol. 105, 3 (1994).

D. F. Hollenbach, L. M. Petrie, and H. L. Dodds, "Vectorization Methods Development for a New Version of the KENO V.a Criticality Safety Code," Nucl. Sci. Eng. 116(3), 147-164, (1994).

C. M. Hopper, "DOE Spent Nuclear Fuel - Nuclear Criticality Safety Challenges and Safeguards Initiatives," Proc. Am. Nucl. Soc. Top. Mtg. on DOE Spent Nuclear Fuel Challenges and Initiatives, Salt Lake City, Utah, December 13-16, 1994.

S. M. Bowman, OFFSCALE: A PC Input Processor for the SCALE Code System, The CSASIN Processor for the Criticality Sequences, NUREG/CR-6182, Vol. 1 (ORNL/TM-12663/V1), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, November 1994.

S. M. Bowman, OFFSCALE: A PC Input Processor for the SCALE Code System, The ORIGNATE Processor for ORIGEN-S, NUREG/CR-6182, Vol. 2 (ORNL/TM-12263/V2), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, November 1994.

O. W. Hermann, J. P. Renier, and C. V. Parks, Technical Support for a Proposed Decay Heat Guide Using SAS2/ORIGEN-S Data, NUREG/CR-5625 (ORNL-6698), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, September 1994.

M. D. DeHart and S. M. Bowman, Validation of the SCALE Broad Structure 44-Group ENDF/B-V Cross-Section Library for Use in Criticality Safety Analyses, NUREG/CR-6102 (ORNL/TM-12460), U. S. Nuclear Regulatory Commission, September 1994.

O. W. Hermann, SAS2H Input for Computing Core Activities of 4.5, 5.0, and 5.5 Weight % 235U Fuel for Sequoyah Nuclear Plant, ORNL/M-3739, Martin Marietta Energy Systems, August 1994.

N. M. Greene, J. W. Arwood, C. V. Parks, and R. Q. Wright, The LAW Library - A Multigroup Cross-Section Library for Use in Radioactive Waste Analysis Calculations, ORNL/TM-12370, Martin Marietta Energy Systems, Oak Ridge National Laboratory, August 1994.

B. W. Moran and B. D. Murphy, Assessment of Technical Criteria for the Termination of IAEA Safeguards on Nuclear Material Contained in Irradiated Waste (U), K/NSP-217.

B. L. Broadhead, R. L. Childs, and R. M. Westfall, "Evaluation of Fernald Plant 6 Criticality Alarm Response," 1994 Annual Meeting American Nuclear Society, New Orleans, La., June 19-23, 1994, Trans. Am. Nucl. Soc. 70, 206-208, (1994).

C. F. Haught, B. Basoglu, R. W. Brewer, H. L. Dodds, and W. C. Jordan, "Analysis of Hypothetical Criticality Excursion Accidents in 10-MW and 20-MW Freezer/Sublimerse," 1994 Annual Meeting American Nuclear Society, New Orleans, La., June 19-23, 1994, Trans. Am. Nucl. Soc. 70, 187-188 (1994).

H. L. Dodds, C. M. Hopper, J. T. Mihalczo, J. T. Thomas, and R. M. Westfall, "Nuclear Criticality Safety Courses at the University of Tennessee- Knoxville," 1994 Annual Meeting American Nuclear Society, New Orleans, La., June 19-23, 1994, Trans. Am. Nucl. Soc. 70, 34-35 (1994).

L. C. Leal, O. W. Hermann, and C. V. Parks, "Automatic Rapid Processing SCALE/SAS2H-Produced Parameter- Dependent Cross Sections for ORIGEN-S," 1994 Annual Meeting American Nuclear Society, New Orleans, La., June 19-23, 1994, Trans. Am. Nucl. Soc. 70, 356-358, (1994).

B. D. Murphy, S. Raman, J. K. Dickens, R. L. Walker and T. D. Newton, "Transmutation Data for Actinide Samples Exposed in the Dounreay Prototype Fast Reactor," 1994 Annual Meeting American Nuclear Society, New Orleans, La., June 19-23, 1994, Trans. Am. Nucl. Soc. 70, 89-91 (1994).

D. F. Hollenbach and C. M. Hopper, "Criticality Safety Study of the MSRE Fuel Drain Tank Cell," 1994 Annual Meeting American Nuclear Society, New Orleans, La., June 19-23, 1994, Trans. Am. Nucl. Soc. 70, 213-215 (1994).

A. Wilkinson et al., "Improved Dose Estimates for Nuclear Criticality Accidents: Preliminary Results," 1994 Annual Meeting American Nuclear Society, New Orleans, La., June 19-23, 1994, Trans. Am. Nucl. Soc. 70, 213-215 (1994).

T. Suto, S. M. Bowman, and C. V. Parks, "The Reactivity Effects of Nuclide Buildup and Decay During Long-Term Fuel Storage," 1994 Inter. High Level Radioactive Waste Management Conference, Las Vegas, Nev., May 22-27, 1994.

D. F. Hollenbach, N. F. Landers, and L. M. Petrie, "KENO Developments," LA-13277-C, in Proc. of Annu. Nucl. Crit. Tech. Safety Project, Williamsburg, Va., May 10-11, 1994.

W. C. Jordan, L. M. Petrie, R. Q. Wright, and C. V. Parks, "Calculation of kinfinity for Homogeneous235U Metal Mixtures: Will the Real kinfinity Please Stand Up?" LA-13277-C, Proc. of Annu. Nucl. Crit. Tech. Safety Project, Williamsburg, Va., May 10-11, 1994.

R. M. Westfall, "Nuclear Data for Criticality Safety," in Proc. Int. Conf. on Nuclear Data for Science and Technology, Gatlinburg, Tenn., May 9-13, 1994.

R. W. Roussin et al., "International Evaluation Cooperation Subgroup 7/Multigroup Cross- Section Processing: Progress and New Directions," Proc. Int. Conf. on Nuclear Data for Science and Technology, Gatlinburg, Tenn., May 9-13, 1994.

B. D. Murphy, S. Raman, J. K. Dickens, R. L. Walker, and T. D. Newton, "Fission-Product Data Analysis from Actinide Samples Exposed in the Dounreay Prototype Fast Reactor," Proc. Int. Conf. on Nuclear Data for Science and Technology, Gatlinburg, Tenn., May 9-13, 1994.

J. E. White et al., "VITAMIN-B6: A Fine-Group Cross Section Library Based on ENDF/B- VI for Radiation Transport Applications," Proc. Int. Conf. on Nuclear Data for Science and Technology, Gatlinburg, Tenn., May 9-13, 1994.

R. Q. Wright, J. E. White, and D. T. Ingersoll, "Fast and Thermal Reactor Data Testing of ENDF/B-VI," Proc. Int. Conf. on Nuclear Data for Science and Technology, Gatlinburg, Tenn., May 9-13, 1994.

B. L. Broadhead, H. F. Locke, and A. Avery, "NEACRP Comparison of Source Term Codes for the Radiation Protection Assessment of Transportation Packages," Proc. 8th International Conference on Radiation Shielding, Arlington, Tex., April 24-28, 1994.

H. Taniuchi and B. L. Broadhead, "Simple Geometry Dose Rate Benchmarks for Spent Fuel Cask Analysis," Proc. 8th International Conference on Radiation Shielding, Arlington, Tex., April 24-28, 1994.

E. C. Beahm and C. F. Weber, "Sludge Washing and Dissolution of ORNL Melton Valley Storage Tank (MVST) Waste," DOE Sludge Workshop, Hanford, Wash., April 11-13, 1994.

P. Cousinou, C. Parks, H. Sannen, H. Schweer, and C. Wilson, "Report of Consultation Meeting on Criticality Safety in the Transport of Radioactive Material," Vienna, Austria, February 14-16, 1994.

E. C. Beahm and C. F. Weber, "Sludge Washing and Dissolution of ORNL Melton Valley Storage Tank (MVST) Waste," Efficient Separations and Processing Integrated Program (ESPIP) Meeting, Dallas, Tex., January 10-11, 1994.

E. C. Beahm et al., "Sludge Dissolution/Leaching - ORNL," Efficient Separations and Processing Integrated Program (ESPIP) Meeting, Dallas, Tex., January 10-11, 1994.

D. F. Hollenbach and C. M. Hopper, Criticality Safety Study of the MSRE Fuel Drain Tank Cell in Building 7503, ORNL/TM-12642, Martin Marietta Energy Systems, Oak Ridge National Laboratory, January 1994.

 

1993

R. M. Westfall and J. F. Alexander, The 1992 Annual Criticality Review Committee Appraisal, ORNL/CF-93/9(ES), Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1993.

T. S. Byun et al., "Principles and practices of irradiation creep experiment using pressurized mini-bellows," Journal of Nuclear Materials 439(439), 108-116 (1993).

W. C. Jordan and H. R. Dyer, Nuclear Criticality Safety Assessment of the Proposed CFC Replacement Coolants, ORNL/TM-12475, Martin Marietta Energy Systems, Oak Ridge National Laboratory, December 1993.

E. C. Beahm, R. A. Lorenz, and C. F. Weber, "Iodine Evolution and pH Control," 1993 Winter Meeting American Nuclear Society, San Francisco, Calif., November 14-18, 1993, Trans. Am. Nucl. Soc. 69, 387 (1993).

M. B. Emmett, "Validation and Verification of the ORNL Monte Carlo Codes for Nuclear Safety Analyses," 1993 Winter Meeting American Nuclear Society, San Francisco, Calif., November 14-18, 1993, Trans. Am. Nucl. Soc. 69, 199-200 (1993).

C. M. Hopper, "Nuclear Criticality Safety Specialist Training and Qualification Programs," 1993 Winter Meeting American Nuclear Society, San Francisco, Calif., November 14-18, 1993, Trans. Am. Nucl. Soc. 69, 255-256 (1993).

T. S. Kress, E. C. Beahm, C. F. Weber, and G. W. Parker, "Fission Product Transport Behavior 2," Nucl. Technol. 101, 262-269 (1993).

D. F. Hollenbach, L. M. Petrie, and N. F. Landers, "KENO-VI: A Monte Carlo Criticality Program with Generalized Quadratic Geometry," Proc. 1993 Topical Meeting on Physics and Methods in Criticality Safety, Nashville, Tenn., September 19-23, 1993.

S. M. Bowman, R. Q. Wright, H. Taniuchi, and M. D. DeHart, "Validation of SCALE-4 Criticality Sequences Using ENDF/B-V Data," Proc. 1993 Topical Meeting on Physics and Methods in Criticality Safety, Nashville, Tenn., September 19-23, 1993.

D. T. Ingersoll, J. E. White, R. Q. Wright, and R. W. Roussin, "Generation and Testing of an ENDF/B-VI Multigroup Cross-Section Library for LWR Shielding Applications," Proc. 8th ASTM-EURATOM Symposium on Reactor Dosimetry, Vail, Colo., August 29-September 3, 1993.

D. T. Ingersoll et al., "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," Proc. 8th ASTM-Euratom Symposium on Reactor Dosimetry, Vail, Colo., August 29-September 3, 1993.

W. A. Rhoades and R. L. Childs, "Application of TORT Three-Dimensional Neutron/Photon Transport Calculations," Proc. 8th ASTM-EURATOM Symposium of Reactor Dosimetry, Vail, Colo., August 29-September 3, 1993.

C. V. Parks, "The SCALE Criticality Safety Analysis Sequences: Status and Future Directions 2," 1993 Annual Meeting American Nuclear Society, San Diego, Calif., June 20-24, 1993, Trans. Am. Nucl. Soc. 68(A), 237-238 (1993).

C. F. Weber and E. C. Beahm, "Iodine Transport in a Severe Accident at the High Flux Isotope Reactor 2," 1993 Annual Meeting American Nuclear Society, San Diego, Calif., June 20-24, 1993, Trans. Am. Nucl. Soc. 68(A), 275 (1993).

S. M. Bowman, O. W. Hermann, and M. C. Brady, "Burnup Credit Validation of SCALE-4 Using Light Water Reactor Criticals," 1993 Annual Meeting American Nuclear Society, San Diego, Calif., June 20-24, 1993, Trans. Am. Nucl. Soc. 68(A), 243 (1993).

S. M. Bowman and H. Taniuchi, "Burnup Credit Validation of SCALE-4 Using Mixed-Oxide Critical Experiments," 1993 Annual Meeting American Nuclear Society, San Diego, Calif., June 20-24, 1993, Trans. Am. Nucl. Soc. 68(A), 241 (1993).

R. Q. Wright, "Revised Evaluations for ENDF/B-VI Revision 2," 1993 Annual Meeting American Nuclear Society, San Diego, Calif., June 20-24, 1993, Trans. Am. Nucl. Soc. 68(A), 468 (1993).

M. B. Emmett, "Status of the MORSE Multigroup Monte Carlo Radiation Transport Code," Proc. Seminar on Advanced Monte Carlo Computer Programs for Radiation Transport, Saclay, France, April 27-29, 1993.

J. S. Tang and B. L. Broadhead, "Development and Application of the Automated Monte Carlo Biasing Procedure in SAS4," Proc. Advanced Monte Carlo Computer Programs for Radiation Transport, OECD-NEA, Saclay, France, April 27-29, 1993.

B. L. Broadhead, C. V. Parks, J. S. Tang, and H. Taniuchi, "Shielding Benchmark Calculations of Selected Spent Fuel Storage Cask Experiments," Vol. 2, pp. 1377-1382 in Proc. of Fourth Annual Inter. Conf. on High Level Radioactive Waste Management, Las Vegas, Nev., April 26-30, 1993.

W. C. Jordan, Validation of SCALE 4.0 - CSAS25 Module and the 27-Group ENDF/B-IV Cross-Section Library for Low-Enriched Uranium Systems, ORNL/CSD/TM-287, Martin Marietta Energy Systems, Oak Ridge National Laboratory, February 1993.

W. C. Jordan, Calculational Criticality Analyses of 10- and 20-MW UF6Freezer/Sublimer Vessels, ORNL/CSD/TM-288, Martin Marietta Energy Systems, Oak Ridge National Laboratory, February 1993.

R. L. Childs and W. A. Rhoades, Theoretical Basis of the Linear Nodal and Linear Characteristics Methods in the TORT Computer Code, ORNL/TM-12246, Martin Marietta Energy Systems, Oak Ridge National Laboratory, January 1993.

S. M. Bowman, Criticality Safety Calculations for Region B of the Millstone Unit No. 2 Spent Fuel Pool, ORNL/M-2574, Martin Marietta Energy Systems, Oak Ridge National Laboratory, January 1993.

 

1992

Y. Y. Azmy et al., Monte Carlo Calculations and Postprocessing of Target Signatures for Smart Weapons Sensors, ORNL/M-2114, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1992.

E. C. Beahm, R. A. Lorenz, and C. F. Weber, Iodine Evolution and pH Control, NUREG/CR-5950 (ORNL/TM-12242), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1992.

R. L. Childs, Evaluation of Neutron Interaction Effects in the Recycle Equipment Test Facility (RETF), ORNL/CFRP-92/20, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1992.

J. E. Horwedel, R. J. Raridon, and R. Q. Wright, "Automated Sensitivity Analysis of an Atmospheric Dispersion Model," Atmos. Environ. 26A(9), 1643-1649 (1992).

R. Q. Wright, "Revised Hafnium Evaluations for ENDF/B-VI," Trans. Am. Nucl. Soc. 65, 422-424 (1992).

D. T. Ingersoll, R. Q. Wright, and C. O. Slater, "Phase II Testing of ENDF/B-VI Shielding Data," Trans. Am. Nucl. Soc. 65, 385-91 (1992).

W. C. Jordan and J. C. Turner, Minimum Mass of Moderator Required for Criticality of Homogeneous Low-Enriched Uranium Systems, ORNL/CSD/TM-284, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1992.

W. A. Rhoades, R. A. Lillie, and M. B. Emmett, Verification of MORSE-SGC on the Cray UNICOS System, ORNL/NPR-92/5, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1992.

W. A. Rhoades, R. L. Childs, and D. T. Ingersoll, "Radiation Exposure Inside Reinforced Concrete Buildings at Nagasaki," Health Phys. 63(5), 510-21 (1992).

C. F. Weber, E. C. Beahm, and J. S. Watson, "Optimal Determination of Rate Coefficients in Multiple Reaction Systems," Comput. Chem. 16(4), 325-333 (1992).

W. C. Jordan and J. C. Turner, Estimated Critical Conditions for UO2F2-H20 Systems in Fully Water- Reflected Spherical Geometry, ORNL/TM-12292, Martin Marietta Energy Systems, Oak Ridge National Laboratory, December 1992.

B. L. Broadhead, R. L. Childs, R. M. Westfall, and C. V. Parks, Evaluation of Criticality Alarm Response at the WEMCO Fernald Site, ORNL/TM-12232, Martin Marietta Energy Systems, Oak Ridge National Laboratory, November 1992.

R. T. Primm, C. M. Hopper, and G. R. Smolen, Criticality Safety Studies for the Storage of Waste from Nuclear Fuel Services in Intercell Storage Wells 2 and 3 of Building 3019, ORNL/TM-12152, Martin Marietta Energy Systems, Oak Ridge National Laboratory, November 1992.

J. E. White, R. Q. Wright, R. W. Roussin, and D. T. Ingersoll, Specifications for the Development of BUGLE-93: An ENDF/B-VI Multigroup Cross Section Library for LWR Shielding and Pressure Vessel Dosimetry, ORNL/TM-12230, Martin Marietta Energy Systems, Oak Ridge National Laboratory, November 1992.

B. L. Broadhead and C. V. Parks, "Assessment of Dose Factor Changes to Spent Fuel Cask Analyses," Proc. 1992 International Conference on Fifty Years of Controlled Nuclear Chain Reaction: Past Present, and Future, Chicago, Ill., November 15-20, 1992.

E. C. Beahm, C. F. Weber, T. S. Kress, and G. W. Parker, "Iodine Chemical Forms in LWR Severe Accidents," Proc. 19th Water Reactor Safety Information Meeting, Bethesda, Md., October 28-30, 1991, NUREG/CP-0119 (1992).

B. L. Broadhead, "Processing of Resonance Parameter Covariance Files," Proc. NEANSC Specialists' Meeting on Evaluation and Processing of Covariance Data, Oak Ridge, Tenn., October 7-9, 1992.

R. E. Maerker, B. L. Broadhead, and J. J. Wagschal, "Needs for Evaluated Covariance Data for Reactor Pressure Vessel Dosimetry," Proc. NEANSC Specialists' Meeting on Evaluation and Processing of Covariance Data, Oak Ridge, Tenn., October 7-9, 1992.

N. M. Greene, W. E. Ford III, L. M. Petrie, and J. W. Arwood, AMPX-77: A Modular Code System for Generating Coupled Multigroup Neutron-Gamma Cross-Section Libraries from ENDF/B-IV and/or ENDF/B-V, ORNL/CSD/TM-283, Martin Marietta Energy Systems, Oak Ridge National Laboratory, October 1992.

C. F. Weber, E. C. Beahm, and T. S. Kress, Models of Iodine Behavior in Reactor Containments, ORNL/TM-12202, Martin Marietta Energy Systems, Oak Ridge National Laboratory, October 1992.

C. Parks, H. Schweer, and C. Wilson, "Issues Concerning Criticality Safety and Overpacks in the Safe Transport of Radioactive Material," Report of Consultants Service Meeting, Vienna, Austria, September 2-4, 1992.

C. V. Parks, "Criticality Safety and Shielding Analysis Methods for Transport Packages," Proc. of DOE Transportation Management Program Workshop, Gaithersburg, Md., August 18-20, 1992.

C. V. Parks, B. L. Broadhead, and M. C. Brady, "Status of Shielding Analysis Methods for Transport Packages," Vol. II, pp. 1650-1653 in Proc. of IRPA8, Montreal, Canada, May 17-22, 1992.

W. A. Rhoades, R. A. Lillie, and M. B. Emmett, Transmission Factors for the Penetration of Neutron and Photon Fluence into Wood-Frame Dwellings, 1990 (TF90), ORNL/TM-12021, Martin Marietta Energy Systems, Oak Ridge National Laboratory, May 1992.

O. W. Hermann, C. V. Parks, and J.-P. Renier, "A Proposed Regulatory Guide Basis for Spent Fuel Decay Heat," Vol. 2, pp. 1662-1669 in Proc. of the Third International Conference on High Level Radioactive Waste Management, Las Vegas, Nev., April 12-16, 1992.

S. M. Bowman, "ORIGNATE - PC Input Processor for ORIGEN-S," Vol. 1, p. 88-92 in Proc. of the Third International Conference on High Level Radioactive Waste Management, Las Vegas, Nev., April 12-16, 1992.

B. L. Broadhead, C. V. Parks, and R. B. Pope, "Assessment of Proposed Dose Factor Changes to Shipping Cask Design and Operation," Vol. 2, pp. 2174-2181 in Proc. of the Third International Conference on High Level Radioactive Waste Management, Las Vegas, Nev., April 12-16, 1992.

B. L. Broadhead, C. V. Parks, D. S. Joy, and J. S. Tang, "Preliminary Assessment of the Benefits of Derating a Cask for Increasing Age/Burnup Capability," Vol. 2, pp. 2182-2189 in Proc. of the Third International Conference on High Level Radioactive Waste Management, Las Vegas, Nev., April 12-16, 1992.

O. W. Hermann and R. Salmon, "Borosilicate Glass (a,n) Sources Used with ORIGEN-Type Calculations," Vol. 2, pp. 1662-1669 in Proc. of the Third International Conference on High Level Radioactive Waste Management, Las Vegas, Nev., April 12-16, 1992.

C. V. Parks, "Overview of ORIGEN2 and ORIGEN-S: Capabilities and Limitations," Vol. 1, pp. 57-63 in Proc. of the Third International Conference on High Level Radioactive Waste Management, Las Vegas, Nev., April 12-16, 1992.

S. Raman, B. L. Broadhead, J. K. Dickens, R. L. Walker, and J. L. Botts, Analyses of Physics Specimens in Fuel Pins 1 and 2 Irradiated in the Dounreay Prototype Fast Reactor, ORNL/6632, Martin Marietta Energy Systems, Oak Ridge National Laboratory, January 1992.

 

1991

C. F. Weber, Calculation of Absorbed Doses to Water Pools in Severe Accident Sequences, NUREG/CR-5808 (ORNL/TM-11970), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1991.

R. M. Westfall, K. S. Joy, and C. M. Horak, The 1990 Annual Criticality Review Committee Appraisal, ORNL/CF-91/53, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1991.

M. L. Williams et al., ENDF/B-V, Revised ENDF/B-V, and ENDF/B-VI Iron Evaluations, NUREG/CR-5648 ( ORNL/TM-11686), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1991.

M. L. Williams et al., "Transport Calculations of Neutron Transmission Through Steel Using ENDF/B-V and ENDF/B-VI Iron Evaluations," Ann. Nucl. Energy, 18(10), 549-565 (1991).

G. D. Kerr, J. S. Tang, and R. L. Childs, "A New Radiation Dosimetry for the 1958 Criticality Accident at the Oak Ridge Y-12 Plant," Health Phys. 60 (1991).

W. A. Rhoades and R. L. Childs, "The Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code," Nucl. Sci. Eng. 107, 397-398 (1991).

G. A. Aramayo et al., Safety Analysis Report for Packaging: The ORNL HFIR Unirradiated Fuel Element Shipping Container, Vol. 1, ORNL/TM-11656/V1, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1991.

G. A. Aramayo et al., Safety Analysis Report for Packaging: The ORNL HFIR Unirradiated Fuel Element Shipping Container, Vol. 2, ORNL/TM-11656/V2, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1991.

M. C. Brady, R. Q. Wright, and T. R. England, Actinide Nuclear Data for Reactor Physics Calculations, ORNL/CSD/TM-266, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1991.

K. F. Eckerman, J. C. Ryman, J. S. Tang, L. R. Williams, and J. V. Pace, "Improved Dose Rate Factors for Exposure to Photons from Contaminated Soil," Health Phys. 60, S83, (1991).

R. L. Childs, L. M. Petrie, and N. F. Landers, A User's Guide for the Starter Computer Program, ORNL/TM-11872, Martin Marietta Energy Systems, Oak Ridge National Laboratory, December 1991.

O. W. Hermann, M. C. Brady, and C. V. Parks, "Validation of Spent Fuel Isotopics Predicted by the SCALE-4 Depletion Sequence," 1991 Winter Meeting American Nuclear Society, San Francisco, Calif., November 10-14, 1991, Trans. Am. Nucl. Soc. 64, 147-149 (1991).

D. F. Hollenbach et al., "Vectorization of the KENO V.a Criticality Safety Code," 1991 Winter Meeting American Nuclear Society, San Francisco, Calif., November 10-14, 1991, Trans. Am. Nucl. Soc. 64, 348-349 (1991).

C. M. Hopper, "ANSI/ANS-8.7-1982(R88) Guide for Nuclear Criticality Safety in the Storage of Fissile Materials," 1991 Winter Meeting American Nuclear Society, San Francisco, Calif., November 10-14, 1991, Trans. Am. Nucl. Soc. 64, 330 (1991).

W. D. Newmeyer, B. Basoglu, D. F. Hollenbach, and H. L. Dodds, "Analysis of a Hypothetical Criticality Accident Involving Dry Highly Enriched Uranium Powder," 1991 Winter Meeting American Nuclear Society, San Francisco, Calif., November 10-14, 1991, Trans. Am. Nucl. Soc. 64, 344 (1991).

R. Q. Wright and J. E. White, "Fast Reactor Data Testing of ENDF/B-VI at ORNL," 1991 Winter Meeting American Nuclear Society, San Francisco, Calif., November 10-14, 1991, Trans. Am. Nucl. Soc. 64, 566-68 (1991).

M. L. Williams et al., "Initial Data Testing of ENDF/B-VI for Thermal Reactor Benchmark Analysis," 1991 Winter Meeting American Nuclear Society, San Francisco, Calif., November 10-14, 1991, Trans. Am. Nucl. Soc. 64, 561-562 (1991).

J. C. Ryman, K. F. Eckerman, J. S. Tang, L. R. Williams, and J. V. Pace, "Organ Doses Due to Exposure to External Radiation Fields," Proc. of 3rd Conf. on Radiation Protection and Dosimetry, Orlando, Fla., October 21-24, 1991.

B. L. Broadhead, "Criticality Safety Review of 2 ½-, 10-, and 14-Ton UF6 Cylinders," Int. Conf. on Nuclear Criticality Safety, Christ Church, Oxford, Great Britain, September 9-13, 1991; also see ORNL/TM-11947, Martin Marietta Energy Systems, Oak Ridge, National Laboratory, October 1991.

C. V. Parks, "Overview of the SCALE-4 Code System," Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, Saclay, France, September 17-19, 1991.

B. L. Broadhead, "An Overview of the QADS Code," Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, September 17-19, 1991, Saclay, France.

S. M. Bowman, "OFFSCALE: PC Input Processor for ORIGEN-S," Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, Saclay, France, September 17-19, 1991.

O. W. Hermann and C. V. Parks, "SAS2H: The SCALE-4 Analysis Sequence for LWR Fuel Depletion," Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, Saclay, France, September 17-19, 1991.

L. M. Petrie, "Vectorization of the KENO V.a Criticality Safety Code," Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, Saclay, France, September 17-19, 1991.

B. L. Broadhead and C. V. Parks, "SCALE-4 Shipping Cask Shielding Applications," Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, Saclay, France, September 17-19, 1991.

L. M. Petrie, N. F. Landers, N. M. Greene, and C. V. Parks, "New SCALE-4 Features Related to Cross-Section Processing," Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, Saclay, France, September 17-19, 1991.

B. L. Broadhead, J. S. Tang, and C. V. Parks, "SAS1 and SAS4, Two New Shielding Analysis Sequences for Spent Fuel Casks," Proc. of Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, Saclay, France, September 17-19, 1991.

C. F. Weber, E. C. Beahm, and T. S. Kress, "Iodine Chemical Forms in LWR Severe Accidents," pp. 414-430, NEA/ CSNI/R(91)15, JAERI, 1992 in Proc. 3rd CSNI Workshop on Iodine Chemistry in Reactor Safety, Tokai-Mura, Japan, September 11-13, 1991.

B. L. Broadhead, Feasibility Assessment of Burnup Credit in the Criticality Analysis of Shipping Casks with Boiling Water Reactor Spent Fuel, ORNL/CSD/TM-268, Martin Marietta Energy Systems, Oak Ridge National Laboratory, August 1991.

S. M. Bowman, Validation of SCALE-4 for a Reference Problem Set, ORNL/M-1332, Martin Marietta Energy Systems, Oak Ridge National Laboratory, July 1991.

O. W. Hermann, SAS2H Input and Assumptions for Cases Computing Isotopic Activities for Sequoyah Nuclear Plant, ORNL/M-1503, Martin Marietta Energy Systems, Oak Ridge National Laboratory, July 1991.

E. C. Beahm, C. F. Weber, T. S. Kress, and G. W. Parker, Iodine Chemical Forms in LWR Severe Accidents, Final Report, NUREG/CR-5732 (ORNL/TM-11861/R3), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, July 1991.

H. R. Dyer, W. C. Jordan, and V. R. Cain, "A Technique for Code Validation for Criticality Safety Calculations," 1991 Annual Meeting American Nuclear Society, Orlando, Fla., June 2-6, 1991, Trans. Am. Nucl. Soc. 63, 238-240 (1991).

T. S. Kress, E. C. Beahm, and C. F. Weber, "Fission Product Behavior," 1991 Annual Meeting American Nuclear Society, Orlando, Fla., June 2-6, 1991, Trans. Am. Nucl. Soc. 63, 260 (1991).

C. O. Slater et al., "Three-Dimensional Radiation Dose Mapping with TORT Computer Code," 1991 Annual Meeting American Nuclear Society, Orlando, Fla., June 2-6, 1991, Trans. Am. Nucl. Soc. 63, 368-370 (1991).

B. L. Broadhead, S. Raman, and J. K. Dickens, "Measurement and Calculation of High Actinide Burnup in the Prototype Fast Reactor (PFR)," 1991 Annual Meeting American Nuclear Society, Orlando, Fla., June 2-6, 1991, Trans. Am. Nucl. Soc. 63, 88-89 (1991).

C. V. Parks, O. W. Hermann, and B. L. Broadhead, "The SCALE Analysis Sequence for LWR Fuel Depletion," Proc. of ANS/ENS International Topical Meeting, Pittsburgh, Pa., April 28-May 1, 1991.

C. V. Parks, L. M. Petrie, J. Manneschmidt, and J. L. Bartley, "SCALE-4: An Updated Version of the Modular Code System for Performing Standardized Computer Analysis For Licensing Evaluation," Proc. of ANS/ENS Inter. Topical Meeting on Advances in Mathematics, Computations, and Reactor Physics, Pittsburgh, Pa., April 28-May 1, 1991.

W. A. Rhoades and R. L. Childs, "TORT - Three-Dimensional Oak Ridge Discrete Ordinates Neutron/Photon Transport Code," Proc. of ANS/ENS Inter. Topical Meeting on Advances in Mathematics, Computations, and Reactor Physics, Pittsburgh, Pa., April 28-May 1, 1991.

S. M. Bowman, Criticality Reference Benchmark Calculations for Burnup Credit Using Spent Fuel Isotopics, ORNL/M-1423, Martin Marietta Energy Systems, Oak Ridge National Laboratory, April 1991.

O. W. Hermann, Data Compiled in Burnup Credit Isotopic Validation Study, ORNL/M-1425, Martin Marietta Energy Systems, Oak Ridge National Laboratory, April 1991.

R. J. Raridon, J. E. Horwedel, and R. Q. Wright, "An Automated Sensitivity Analysis Procedure Applied to an Atmospheric Dispersion Model," Annu. Meet. Am. Assoc. Adv. Sci., Wash., D.C., February 14-19, 1991.

 

1990

T. L. Sanders and R. M. Westfall, "Feasibility and Incentives for Burnup Credit in Spent Fuel Transport Casks, Nucl. Sci. Eng. 104, 66-77 (1990).

R. M. Westfall, 1989 Criticality Appraisal, ORNL/CF-90/278, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1990.

M. L. Williams, R. L. Childs, and M. Asagari, Analysis of H. B. Robinson PWR Vessel Fluence for Cycle 10 Utilizing Partial Length Shield Assemblies, NUREG/CR-5530 ORNL/TM-11476, U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1990.

R. G. Alsmiller, F. S. Alsmiller, and O. W. Hermann, "Calculated Inclusive Neutron Production from 400 GeV Proton-Nucleus Collisions," Nucl. Instrum. Methods Phys. Res. A: Accelerators, Spectrometers, Detectors and Associated Equipment, 286, Issues 1-2, 73-75 (1990).

R. G. Alsmiller, F. S. Alsmiller, and O. W. Hermann, "The High-Energy Transport Code HETC88 and Comparisons with Experimental Data," Nucl. Instrum. Methods Phys. Res. A: Accelerators, Spectrometers, Detectors and Associated Equipment, 295, Issue 3, 337-343 (1990).

R. G. Alsmiller et al., "Calculated Neutron Spectrum in the TEVATRON Tunnel and Comparison with Experimental Data," Nucl. Instrum. Methods Phys. Res., A 295, 99-101 (1990).

W. E. Ford, III, et al., ANSL-V: ENDF/B-V Based Multigroup Cross-Section Libraries for Advanced Neutron Source (ANS) Reactor Studies, ORNL-6618, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1990.

W. C. Jordan, R. C. Robinson, B. E. Lewis, M. J. Haire, and H. Funabashi, Criticality Analysis of a Continuous Rotary Dissolver, ORNL/TM-11191, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1990.

W. C. Jordan, G. R. Smolen, M. J. Haire, and H. Funabashi, Plan for the CFRP Criticality Safety Evaluation for the DOE/PNC Joint Collaboration Program in Reprocessing Technology, ORNL/CFRP-88/29, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1990.

S. A. McElhaney, M. L. Bauer, J. H. Todd, M. B. Emmett, M. M. Chiles, "Monte Carlo and Experimental Evaluation of BC454 for Use as a Multienergy Neutron Detector," IEEE Trans. Nucl. Sci. 37, 1351-58 (1990).

B. L. Broadhead, M. C. Brady, and C. V. Parks, Benchmark Shielding Calculations for the NEACRP Working Group on Shielding Assessment of Transportation Packages, ORNL/CSD/TM-272, Martin Marietta Energy Systems, Oak Ridge National Laboratory, November 1990.

S. M. Bowman, C. V. Parks, and S. R. Bierman, "Validation of SCALE-4 for LWR Fuel in Transportation and Storage Cask Conditions," 1990 Winter Meeting American Nuclear Society, Washington, D.C., November 11-15, 1990, Trans. Am. Nucl. Soc. 62, 338-340 (1990).

M. C. Brady, C. V. Parks, and C. R. Marotta, "End Effects in the Criticality Analysis of Burnup Credit Casks," 1990 Winter Meeting American Nuclear Society, Washington, D.C., November 11-15, 1990, Trans. Am. Nucl. Soc. 62, 317 (1990).

B. L. Broadhead, "Burnup Credit Feasibility for BWR Spent Fuel Shipments," 1990 Winter Meeting American Nuclear Society, Washington, D.C., November 11-15, 1990, Trans. Am. Nucl. Soc. 62, 319-321 (1990).

B. L. Broadhead, M. C. Brady, and C. V. Parks, "Benchmarking of Dose Rate Calculations for Spent Fuel Transportation Casks," 1990 Winter Meeting American Nuclear Society, Washington, D.C., November 11-15, 1990, Trans. Am. Nucl. Soc. 62, 435 (1990).

J. T. Mihalczo and B. L. Broadhead, "Burnup Credit Allowance in the Storage and Transport of LWR Fuel- Pool, Measurements, and Applications," 1990 Winter Meeting American Nuclear Society, Washington, D.C., November 11-15, 1990, Trans. Am. Nucl. Soc. 62, 322-324 (1990).

J.-P. Renier and C. V. Parks, "Reactor Critical Calculations for Validation of Burnup Credit Analysis Methods," 1990 Winter Meeting American Nuclear Society, Washington, D.C., November 11-15, 1990, Trans. Am. Nucl. Soc. 62, 308 (1990).

R. M. Westfall, R. Q. Wright, and J. Greenborg, "Status of Standard for Neutron Skyshine Calculation and Measurement," 1990 Winter Meeting American Nuclear Society, Washington, D.C., November 11-15, 1990, Trans. Am. Nucl. Soc. 62, 433-435 (1990).

F. S. Alsmiller, R. G. Alsmiller, T. A. Gabriel, and O. W. Hermann, "HECC: A Phenomenological Hadron-Nucleus High Energy Cascade Collision Model," Symposium on Detector Research and Development for the SSC, Fort Worth, Tex., October 15-18, 1990.

D. F. Hollenbach, K. H. Reynolds, H. L. Dodds, N. F. Landers, and L. M. Petrie, "An Improved Method for Storing and Retrieving Tabulated Data in a Scalar Monte Carlo Code," 1990 Annual Meeting American Nuclear Society, Nashville, Tenn., June 10-14, 1990, Trans. Am. Nucl. Soc. 61, 191 (1990).

K. H. Reynolds, D. A. Tollefson, D. F. Hollenbach, and H. L. Dodds, "Criticality Safety Studies of a Proposed Uranium-Zirconium Alloy Fuel Fabrication Facility," 1990 Annual Meeting American Nuclear Society, Nashville, Tenn., June 10-14, 1990, Trans. Am. Nucl. Soc. 61, 185 (1990).

C. M. Hopper and J.-P. Renier, "Expanded and Applied Sixteen Neutron-Energy-Group Cross-Section Library," 1990 Annual Meeting American Nuclear Society, Nashville, Tenn., June 10-14, 1990, Trans. Am. Nucl. Soc. 61, 186-88 (1990).

B. L. Broadhead, QADS: A Multidimensional Point Kernel Analysis Module, NUREG/CR-5468 (ORNL/CSD/TM-270), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, May 1990.

W. H. Lake, T. L. Sanders, and C. V. Parks, "Investigation of Burnup Credit Allowance in the Criticality Safety Evaluation of Spent Fuel Casks," Vol. 2, pp. 777-784 in Proc. Inter. Topical Mtg. on High Level Radioactive Waste Management, Las Vegas, Nev., April 8-12, 1990.

J.-P. Renier and C. V. Parks, Executive Summary: Reactor Critical Benchmark Calculations for Burnup Credit Applications, ORNL/M-1073, Martin Marietta Energy Systems, Oak Ridge National Laboratory, April 1990.

R. G. Alsmiller et al., "The CALOR89 Calorimeter Design and Analysis Code System," Workshop on Physics and Detector Simulation, Dallas, Tex., January 8-19, 1990.

 

 

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