Reactor and Nuclear Systems Division

Reactor and Nuclear Systems Division
1986 - 1989 Publications

[1986]   [1987]   [1988]   [1989]

1986

R. C. Berkan et al., "Preliminary Design Concept for Axial Xenon Oscillation Modeling and Control," Am. Nucl. Soc. 1986 Student Design Competition, Graduate Students' Entry.

J. A. Bucholz and R. L. Childs, Preconceptual Shielding Design Analyses for the Lower Portion of the MHTGR Reactor System Incorporating a 350-MWth Annular Prismatic Core, ORNL/GCR-86/1, 1986.

J. A. Bucholz and R. L. Childs, Preconceptual Shielding Design Analyses for the Upper Portion of the MHTGR Reactor System Incorporating a 350-MWth Annular Prismatic Core, ORNL/GCR-86/4, 1986.

S. N. Cramer and J. S. Tang, Variance Reduction Methods Applied to Deep-Penetration Monte Carlo Problems, ORNL/TM-9643, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1986.

O. W. Hermann and C. W. Alexander, A Review of Spent-Fuel Photon and Neutron Source Spectra, ORNL/CSD/TM-205, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1986.

R. E. Maerker, B. L. Broadhead, B. A. Worley, M. L. Williams, and J. J. Wagschal, "Application of the LEPRICON Unfolding Procedure to the Arkansas Nuclear One - Unit 1 Reactor," Nucl. Sci. Eng. 93, 137-170 (1986).

R. E. Maerker, M. L. Williams, and B. L. Broadhead, "Accounting for Changing Source Distributions in Light Water Reactor Surveillance Dosimetry Analysis," Nucl. Sci. Eng. 94, 291-308 (1986).

C. W. Miller, A. L. Sioreen, C. L. Begovich, and O. W. Hermann, ANEMOS: A Computer Code to Estimate Air Concentrations and Ground Deposition Rates for Atmospheric Nuclides Emitted from Multiple Operating Sources, ORNL-5913, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1986.

E. M. Oblow, F. G. Pin, and R. Q. Wright, "Sensitivity Analysis Using Computer Calculus: A Nuclear Waste Isolation Application," Nucl. Sci. Eng. 94, 46-65 (1986).

F. G. Pin, E. M. Oblow, and R. Q. Wright, Automated Sensitivity Analysis Using the GRESS Language, ORNL-6148, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1986.

F. G. Pin, B. A. Worley, E. M. Oblow, R. Q. Wright, and W. V. Harper, "An Automated Sensitivity Analysis Procedure for the Performance Assessment of Nuclear Waste Isolation Systems," Nucl. Chem. Waste Manage. 6, 255-63 (1986).

J. L Thompson, M. B. Emmett, and H. L. Dodds, Development and Evaluation of DOTTOR, A Computer code to Couple Two-Dimensional to Three-Dimensional Discrete Ordinates Calculations, ORNL/TM-9919, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1986.

B. A. Worley, R. Q. Wright, F. G. Pin, and W. V. Harper, "Application of an Automated Procedure for Adding a Comprehensive Sensitivity Calculation Capability to the ORIGEN2 Point Depletion and Radioactive Decay Code," Nucl. Sci. Eng. 94, 180-91 (1986).

W. C. Jordan, N. F. Landers, and L. M. Petrie, Validation of KENO V.a Comparison with Critical Experiments, ORNL/CSD/TM-238 , Martin Marietta Energy Systems, Oak Ridge National Laboratory, December 1986.

J. C. Ryman et al., "A Code System to Compute Radiation Dose in Human Phantoms," 1986 Winter Meeting of the American Nuclear Society, Washington, D.C., November 16-20, 1986, Trans. Am. Nucl. Soc. 53, 37-38 (1986).

E. C. Beahm, W. E. Shockley, and C. F. Weber, "Chemistry and Transport of Iodine in Containment," Proc. International Symposium Source Term Evaluation for Accident Conditions, Columbus, Ohio, October 28-November 1, 1985, IAEA-5M-281-41 (1986).

C. R. Hyman and C. F. Weber, "Effects of Lateral Separation of Oxidic and Metallic Core Debris on the BWR MK I Containment Drywell Floor," Trans. of 14th Water Reactor Safety Information Meeting, Gaithersburg, Md., October 27-31, 1986, NUREG/CP-0081, U. S. Nuclear Regulatory Commission, 1986.

C. V. Parks, G. E. Giles, K. W. Childs, and C. B. Bryan, "Heat Transfer Analysis Capabilities of the SCALE Computational System," Proc. OECD Workshop on SCALE-3 Modular System, Saclay, France, June 24-27, 1986, Newsletter of the NEA Data Bank No. 33, pp. 67-95, October 1986.

C. V. Parks, O. W. Hermann, and J. C. Ryman, "Evaluation of Spent Fuel Isotopics, Radiation Spectra, and Decay Heat Using the SCALE Computational System," Proc. OECD Workshop on SCALE-3 Modular System, Saclay, France, June 24-27, 1986, Newsletter of the NEA Data Bank No. 33, pp. 96-124, October 1986.

C. V. Parks, L. M. Petrie, N. F. Landers, and J. A. Bucholz, "Computational Methods for Criticality Safety Analysis within the SCALE System," Proc. OECD Workshop on SCALE-3 Modular System, Saclay, France, June 24-27, 1986, Newsletter of the NEA Data Bank No. 33, pp. 31-44, October 1986.

C. V. Parks, J. S. Tang, O. W. Hermann, J. A. Bucholz, and M. B. Emmett, "Shielding Analysis Methods Available in the SCALE Computational System," Proc. OECD Workshop on SCALE-3 Modular System, Saclay, France, June 24-27, 1986, Newsletter of the NEA Data Bank No. 33, pp. 45-66, October 1986.

C. V. Parks and R. M. Westfall, "History and Overview of the SCALE System," Proc. OECD Workshop on SCALE-3 Modular System, Saclay, France, June 24-27, 1986, Newsletter of the NEA Data Bank No. 33, pp. 5-19, October 1986.

R. M. Westfall, "Cross-Section Library and Processing Techniques Within the SCALE System," Proc. OECD Workshop on SCALE-3 Modular System, Saclay, France, June 24-27, 1986, Newsletter of the NEA Data Bank, No. 33, October 1986.

C. R. Hyman, C. F. Weber, and S. A. Hodge, "Effects of Lateral Separation of Oxidic and Metallic Core Debris on the BWR MK I Containment Drywell Floor," Specialist Meeting on Core Debris/Concrete Interactions, EPRI Headquarters, September 3-5, 1986.

B. A. Worley, R. Q. Wright, and F. G. Pin, A Finite-Line Heat Transfer Code with Automated Sensitivity-Calculation Capability, ORNL/TM-9975, Martin Marietta Energy Systems, Oak Ridge National Laboratory, September 1986.

C. V. Parks, Adjoint-Based Sensitivity Analysis for Reactor Safety Applications, ORNL/CSD/TM-231, Martin Marietta Energy Systems, Oak Ridge National Laboratory, August 1986.

L. D. Bates et al., Summary of the Technical Review of the Safety Analysis Reports for Packaging (SARP) for the Transnuclear Transport/Storage Casks: TN-BRP and TN-REG, ORNL/TM-9889, Martin Marietta Energy Systems, Oak Ridge National Laboratory, July 1986.

R. M. Westfall, "Lecture Notes for SCALE Workshop: Session 2 - Functional Modules for Cross-Section Preparation," OECD/NEA Data Bank Workshop on the SCALE System, Saclay, France, June 24 – 27, 1986.

R. M. Westfall, "Lecture Notes for SCALE Workshop: Session 7a -Data Libraries -CESAR, Cross Sections, Standard Compositions," OECD/NEA Data Bank Workshop on the SCALE System, Saclay, France, June 24 – 27, 1986.

R. M. Westfall and C. V. Parks, "TMI-2 Reactor Coolant System Criticality Analyses," 1986 Annual Meeting of the American Nuclear Society, Reno, Nev., June 15-19, 1986, Trans. Am. Nucl. Soc. 52, 454-56 (1986).

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," 1986 Annual Meeting of the American Nuclear Society, Reno, Nev., June 15-19, 1986, Trans. Am. Nucl. Soc. 52, 114-16 (1986).

R. G. Alsmiller, F. S. Alsmiller, T. A. Gabriel, and O. W. Hermann, "Nucleon-Meson Cascade Calculations by Monte Carlo Methods," 1986 Annual Meeting of the American Nuclear Society, Reno, Nev., June 15-19, 1986, Trans. Am. Nucl. Soc. 52, 385-87 (1986).

B. A. Worley, R. Q. Wright, and F. G. Pin, "A Version of ORIGEN2 with Automated Sensitivity-Calculation Capability," 1986 Annual Meeting of the American Nuclear Society, Reno, Nev., June 15-19, 1986, Trans. Am. Nucl. Soc. 52, 438-39 (1986).

C. V. Parks, "Application of SCALE to Analysis of Spent Fuel Casks," Vol. 2, pp. 385-393 in Proc. of IAEA Inter. Symp. on Packaging and Transport of Radioactive Materials (PATRAM '86), June 16-20, 1986, IAEA-SM-286/62P (1986).

R. M. Westfall, "Lecture Notes for SCALE Workshop: Session 2 - Functional Modules for Cross-Section Preparation," RSIC/TDMC Workshop SCALE Computational System, Oak Ridge, Tenn., April 15 – 18, 1986.

O. W. Hermann, C. V. Parks, and J. C. Ryman, "Spent Fuel Decay Heat Calculations Using ORIGEN-S," Vol. 2, p. W-97 in Proc. Third Inter. Spent Fuel Storage Technology Symposium/Workshop, April 8-10, 1986, CONF-860417 (1986).

C. V. Parks, "Criticality and Shielding Analysis of Spent Fuel Storage Packages," Vol. 2, p. W-183 in Proc. Third Inter. Spent Fuel Storage Technology Symposium/ Workshop, April 8-10, 1986, CONF-860417 (1986).

R. E. Maerker, B. L. Broadhead, B. A. Worley, M. L. Williams, and J. J. Wagschal, Application of the LEPRICON Methodology to the Arkansas Nuclear One, Unit 1 Reactor, EPRI NP-4469, Electric Power Research Institute, February 1986.

1987

R. T. Santoro, J. Marnes, 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," Fusion Technol. 11, 420-428 (1987).

E. C. Beahm, C. F. Weber, T. S. Kress, and R. J. Anderman, Calculations of Iodine Source Terms in Support of NUREG-0956, ORNL/NRC/LTR-86/17, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1987.

C. R. Hyman, C. F. Weber, and S. A. Hodge, Effects of Lateral Separation of Oxidic and Metallic Core Debris on the BWR MK I Containment Drywell Floor, NUREG/CR-4610 (ORNL/TM-10057), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1987.

C. R. Hyman, C. F. Weber, and S. A. Hodge, "Effects of Lateral Separation of Oxidic and Metallic Core Debris on the BWR MK I Containment Drywell Floor," Committee on Safety of Nuclear Installations (CSNI), Specialists Meeting on Core Debris/Concrete Interactions, EPRI NP-5054-SR, Electric Power Research Institute, 1987.

W. A. Rhoades and R. L. Childs, The TORT Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code, ORNL/6268, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1987.

C. V. Parks, Summary Description of the SCALE Modular Code System, NUREG/CR-5033 (ORNL/CSD/TM-252), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, December 1987.

R. L. Childs and W. A. Rhoades, "The Linear Characteristic Method in XYZ Geometry," 1987 Winter Meeting of the American Nuclear Society, Los Angeles, Calif., November 15-19, 1987, Trans. Am. Nucl. Soc. 55, 352-354 (1987).

H. R. Dyer and R. M. Westfall, "KENO V.a Validation of Fuel Pin Experiments," 1987 Winter Meeting of the American Nuclear Society, Los Angeles, Calif., November 15-19, 1987, Trans. Am. Nucl. Soc. 55, 382-385 (1987).

W. E. Ford III et al., "ANSL-V: ENDF/B-V Based Multigroup Cross-Section Libraries for Advanced Neutron Source (ANS) Reactor Studies," 1987 Winter Meeting of the American Nuclear Society, Los Angeles, Calif., November 15-19, 1987, Trans. Am. Nucl. Soc. 55, 614-616 (1987).

J. W. Arwood et al., "Preparation and Benchmarking of ANSL-V Cross Sections for Advanced Neutron Source Reactor Studies," 1987 Winter Meeting of the American Nuclear Society, Los Angeles, Calif., November 15-19, 1987, Trans. Am. Nucl. Soc. 55, 614-616 (1987).

T. L. Sanders, R. M. Westfall, and E. L. Wilmot, "Burnup Credit in the Design of Spent-Fuel Shipping Casks," 1987 Winter Meeting of the American Nuclear Society, Los Angeles, Calif., November 15-19, 1987, Trans. Am. Nucl. Soc. 55, 391-392 (1987).

C. V. Parks, J. V. Pace III, and O. W. Hermann, "Characterization of Neutron Sources from Spent Fuel Casks," 1987 Winter Meeting of the American Nuclear Society, Los Angeles, Calif., November 15-19, 1987, Trans. Am. Nucl. Soc. 55, 534-535 (1987).

D. Ugolini, L. M. Petrie, and H. L. Dodds, "Evaluation of a Simplified Version of KENO V.a on a Parallel Processor Computer," 1987 Winter Meeting of the American Nuclear Society, Los Angeles, Calif., November 15-19, 1987, Trans. Am. Nucl. Soc. 55, 326-327 (1987)

W. A. Rhoades and R. L. Childs, "Sn Transport Calculations on Vector and Parallel Processors," 1987 Winter Meeting of the American Nuclear Society, Los Angeles, Calif., November 15-19, 1987, Trans. Am. Nucl. Soc. 55, 320 (1987).

R. M. Westfall and D. S. Williams, "Projected Standard on Neutron Skyshine," 1987 Winter Meeting of the American Nuclear Society, Los Angeles, Calif., November 15-19, 1987, Trans. Am. Nucl. Soc. 55, 531-532 (1987).

S. P. Cerne, O. W. Hermann, and R. M. Westfall, Reactivity and Isotopic Composition of Spent PWR Fuel as a Function of Initial Enrichment, Burnup, and Cooling Time, ORNL/CSD/TM-244, Martin Marietta Energy Systems, Oak Ridge National Laboratory, October 1987.

R. W. Barber, B. P. Brown, and C. M. Hopper, "The United States Department of Energy Office of Nuclear Safety National Criticality Safety Program and Activities," Int. Seminar on Nuclear Criticality Safety, Tokyo, Japan, October 19-23, 1987.

B. A. Worley et al., "Deterministic Methods for Sensitivity and Uncertainty Analysis in Large-Scale Computer Models," in Proc. Conf. on Geostatistical, Sensitivity, and Uncertainty Analysis for Groundwater Flow and Radionuclide Transport Modeling, San Francisco, Calif., September 15-17, 1987.

B. A. Worley et al., "Deterministic Methods for Sensitivity and Uncertainty Analysis in Large-Scale Computer Models," DOE/AECL Sensitivity and Uncertainty Conf., San Francisco, Calif., September 9-14, 1987.

T. S. Kress, E. C. Beahm, and C. F. Weber, "Modeling of the Transport of Vapor Fission Product Species to Aerosols," Workshop on Water-Cooled Reactor Aerosol Code Evaluation and Uncertainty Assessment, Brussels, Belgium, September 9-11, 1987.

T. A. Gabriel et al., "CALOR87: HETC87, MICAP, EGS4, and SPECT, A Code System for Analyzing Detectors for Use in High Energy Physics Experiments," in Proc. Workshop on Detector Simulation, Argonne National Laboratory, Argonne, Ill., August 24-28, 1987.

T. L. Sanders, R. M. Westfall, and R. H. Jones, Feasibility and Incentives for the Consideration of Spent Fuel Operating Histories in the Criticality Analysis of Spent Fuel Shipping Casks, SAND-87-0151, Sandia National Laboratories, August 1987.

C. M. Hopper, "U.S. DOT Specification 6M Radioactive Fissile Material Package Nuclear Criticality Safety Re-Evaluation," IAEA Int. Symp. Packaging and Transport of Radioactive Materials, Davos, Switzerland, June 16-20, 1986, IAEA-SM-286/222, 1987.

O. W. Hermann, C. V. Parks, and S. B. Ludwig, "ORIGEN-S (a, n) Neutron Source Spectra in Borosilicate Glass containing HLW," 1987 Annual Meeting of the American Nuclear Society, Dallas, Tex., June 7-11, 1987, Trans. Am. Nucl. Soc. 54, 63-64 (1987).

B. L. Broadhead and C. V. Parks, "Point Kernel Versus Radiation Transport for Iron Deep Penetration Problems," 1987 Annual Meeting of the American Nuclear Society, Dallas, Tex., June 7-11, 1987, Trans. Am. Nucl. Soc. 54, 295-296 (1987).

R. A. Lillie, B. L. Broadhead, J. V. Pace III, and D. G. Cacuci, "Sensitivity/Uncertainty Analysis for the Nagasaki Dosimetry Reevaluation Effort," Vol. 2, pp. 139-148 in Proc. of Theory and Practices in Radiation Protection and Shielding, Knoxville, Tenn., April 22-24, 1987.

C. V. Parks et al., "Intercomparison of Cross-Section Libraries Used for Spent Fuel Cask Shielding Analyses," Vol. 2, pp. 559-569 in Proc. of Theory and Practices in Radiation Protection and Shielding, Knoxville, Tenn., April 22-24, 1987.

B. L. Broadhead, R. A. Lillie, J. V. Pace III, and D. G. Cacuci, "Sensitivity/Uncertainty Analysis for the Hiroshima Dosimetry Reevaluation Effort," Vol. 2, pp. 149-157 in Proc. of Theory and Practices in Radiation Protection and Shielding, Knoxville, Tenn., April 22-24, 1987.

F. S. Alsmiller, R. G. Alsmiller, and O. W. Hermann, "Low-Energy Particle Production and Residual Nuclei Production from High-Energy Hadron-Nucleus Collisions," pp. 444 in Proc. Am. Nucl. Soc. Top. Conf. on Theory and Practices in Radiation Protection and Shielding, Knoxville, Tenn., April 22-24, 1987.

R. G. Alsmiller, F. S. Alsmiller, T. A. Gabriel, and O. W. Hermann, "Modifications of the High-Energy Transport Code (HETC) and Comparisons with Experimental Results," pp. 399 in Proc. Am. Nucl. Soc. Top. Conf. on Theory and Practices in Radiation Protection and Shielding, Knoxville, Tenn., April 22-24, 1987.

J. S. Tang, C. V. Parks, and O. W. Hermann, "Automated Shielding Analysis Sequences for Spent Fuel Casks," Vol. 2, pp. 549-558 in Proc. of Theory and Practices in Radiation Protection and Shielding, Knoxville, Tenn., April 22-24, 1987.

T. L. Sanders, R. M. Westfall, and R. H. Jones, Incentives for the Allowance of Burnup Credit in the Design of Spent Nuclear Fuel Shipping Casks, SAND-87-0232C, Sandia National Laboratories, March 1987.

D. B. Reister and R. Q. Wright, Sensitivity Analysis of ORION, ORNL/TM-10198, Martin Marietta Energy Systems, Oak Ridge National Laboratory, January 1987.

1988

J. A. Bucholz and R. L. Childs, B-10 Depletion in the Borated Steel Pins Located in the Permanent Side Reflector of the MHTGR, ORNL/GCR-88/6, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1988.

D. C. Kaul et al., "Organ Dosimetry, Reassessment of Atomic Bomb Radiation Dosimetry in Hiroshima and Nagasaki, Final Report," Radiation Effects Research Foundation Publ. Vol. 1, pp. 306-404 (1988).

R. A. Lillie, B. L. Broadhead, J. V. Pace III, and D. G. Cacuci, "Sensitivity/Uncertainty Analysis for Free-in-Air Tissue Kerma Due to Initial Radiation at Hiroshima and Nagasaki," Nucl. Sci. Eng. 100, 105-124 (1988).

M. C. Brady, O. W. Hermann, and W. B. Wilson, "Comparison of Radiation Sources from Selected Point Depletion Codes," Trans. Am. Nucl. Soc. 57, 226-29 (1988).

C. V. Parks and R. M. Westfall, "Criticality Analysis Support for the TMI-2 Fuel Removal Operations," Trans. Am. Nucl. Soc. 57, 507-508 (1988).

R. G. Alsmiller, F. S. Alsmiller, T. A. Gabriel, O. W. Hermann, and B. L. Bishop, "The Modified High-Energy Transport Code, HETC, and Design Calculations for the SSC," Trans. Am. Nucl. Soc. 56, 270-271 (1988).

C. W. A. Rhoades and R. L. Childs, "The DORT Two-Dimensional Discrete Ordinates Transport Code," Nucl. Sci. Eng. 99, 88-89 (1988).

J. S. Tang and T. J. Hoffman, "Monte Carlo Shielding Analyses Using an Automated Biasing Procedure," Nucl. Sci. Eng. 99, 329-42 (1988).

R. M. Westfall, H. R. Dyer, and L. M. Petrie, Assessment of Criticality Computational Software for the U.S. Department of Energy Office of Civilian Radioactive Waste Management Applications, ORNL/CSD/TM-247, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1988.

T. S. Kress, E. C. Beahm, W. E. Shockley, and C. F. Weber, "Trends Status," Trends Status, Severe Accident Research Partners Meet., Washington, D.C., October 17-21, 1988.

C. V. Parks, B. L. Broadhead, and J. S. Tang, "Comparison of Calculational Methods for Analysis of Spent Fuel Cask Shielding ," Vol. 3, p. 807-816 in Proc. 7th International Conference on Radiation Shielding, Bournemouth, Great Britain, September 12-16, 1988.

R. L. Childs, W. A. Rhoades, and L. R. Williams, "Three-Dimensional Calculations of Neutron Streaming in the Beam Tubes of the ORNL HFIR Reactor," V. 2, pp. 409-18 in Proc. 7th International Conference on Radiation Shielding (ICRS7), Bournemouth, Great Britain, September 12-16, 1988.

W. A. Rhoades, R. L. Childs, and D. T. Ingersoll, "New Dose-Mortality Data Based on 3-D Radiation Shielding Calculation for Concrete Buildings at Nagasaki," V. 3, pp. 1145-154 in Proc. 7th International Conference on Radiation Shielding (ICRS7), Bournemouth, Great Britain, September 12-16, 1988.

C. V. Parks et al., Assessment of Shielding Analysis Methods, Codes, and Data for Spent Fuel Transport/Storage Applications, ORNL/CSD/TM-246, Martin Marietta Energy System, Oak Ridge National Laboratory, September 1988.

B. A. Worley et al., "Deterministic Sensitivity and Uncertainty Analysis for Large-Scale Computer Models," 10th Annual DOE Low-Level Waste Management Conf., Session II: Site Performance Assessment, Denver, Colo., August 30-September 1, 1988.

E. C. Beahm et al., "Chemistry and Mass Transport of Iodine in Containment," Meet. Am. Chem. Soc., Toronto, Canada, June 4-9, 1988.

W. C. Jordan, C. V. Parks, and L. M. Petrie, "An Improved Dancoff Correction Factor for the SCALE Code System," Trans. Am. Nucl. Soc. 56, 324-325 (1988).

E. C. Beahm, C. F. Weber, S. R. Daish, and T. S. Kress, "TRENDS: Improvements and Evaluation," NRC Severe Accident Research Partners Review Meeting, April 25-29, 1988, Sandia National Laboratory, Albuquerque, N. Mex.

M. J. Haire, M. W. Waddell, and W. C. Jordan, "ICFRP Dissolver Concept: Criticality Analysis," USDOE./PNC Specialists' and Program Review Meeting, February 16-26, 1988, ORNL, Oak Ridge, Tenn. (Closed Meeting)

1989

M. C. Brady, O. W. Hermann, and W. B. Wilson, Comparison of Radiation Spectra from Selected Source-Term Computer Codes, ORNL/CSD/TM-259, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1989.

M. B. Emmett and W. A. Rhoades, "MASH, The Monte Carlo Adjoint Shielding Code," Proc. Conf. on Advances in Nuclear Engineering Computation and Radiation Shielding, Vol. 1, pp. 42:1-42:10 (1989).

B. A. Worley et al., "Deterministic Sensitivity and Uncertainty Analysis for Large-Scale Computer Models," Proc. NEA Probabilistic System Assessment Codes User Group, Paris, France, November 29-December 2, 1988 (1989).

N. M. Greene, J. W. Arwood, and C. V. Parks, "The LAW Library - A Multigroup Cross-Section Library for Use in Radioactive Waste Analysis Calculations," Proc. International Topical Meeting on Safety Margins in Criticality Safety, San Francisco, Calif., November 26-30, 1989.

N. F. Landers and L. M. Petrie, "Uncertainties Associated with the Use of the KENO Monte Carlo Criticality Codes," pp. 289-96 in Proc. International Topical Meeting on Safety Margins in Criticality Safety, San Francisco, Calif., November 26-30, 1989.

C. V. Parks and P. B. Fox, "Demonstration of Criticality Safety for the Modified TN-REG and TN-BRP Transport/Storage Casks," pp. 331-339 in Proc. International Topical Meeting on Safety Margins in Criticality Safety, San Francisco, Calif., November 26-30, 1989.

L. C. Leal, G. de Saussure, R. B. Perez, and R. Q. Wright, "Test of the ENDF/B Unresolved Resonance Formalism for 235U," Trans. Am. Nucl. Soc. 60, 620-21 (1989).

C. V. Parks, "Evaluation of Shielding Analysis Methods for Spent Fuel Casks," Trans. Am. Nucl. Soc. 60, 522-523 (1989).

C. V. Parks, R. M. Westfall, and B. L. Broadhead, "Criticality Analysis Support for the Three-Mile Island Unit 2 Fuel Removal Operations," Nucl. Tech. 87, 660-677 (November 1989).

C. V. Parks, Proc. of a Workshop on the Use of Burnup Credit in Spent Fuel Transport Casks, Washington, D.C., February 21-22, 1988, SAND-89-0018, October 1989.

R. G. Alsmiller, F. S. Alsmiller, and O. W. Hermann, Calculated Inclusive Neutron Production from 400 GeV Proton-Nucleus Collision, ORNL/TM-11257, Martin Marietta Energy Systems, Oak Ridge National Laboratory, August 1989.

S. A. McElhaney, M. L. Bauer, J. H. Todd, M. B. Emmett, and M. M. Chiles, "Monte Carlo and Experimental Evaluation of BC454 for Use as a Multienergy Neutron Detector," 34th Ann. Meet. Health Phys. Soc., Albuquerque, N. Mex., June 25-29, 1989.

M. C. Brady, J. P. Renier, C. V. Parks, and T. L. Sanders, "Comparison of Analysis Methods for Burnup Credit Applications," Proc. 9th Inter. Symp. on Packaging and Trans. of Radioactive Materials, Dubrovnik, Washington, D.C., June 11-16, 1989, CONF-890631, Vol. 2, pp. 771-778 (1989).

R. Q. Wright, M. L. Williams, and C. O. Slater, "Impact of U-235 (MAT 9235) Evaluation on k-eff of Thermal Systems," 1989 Annual Meeting American Nuclear Society, Atlanta, Ga., June 4-8, 1989, Trans. Am. Nucl. Soc. 59, 343-44 (1989).

E. C. Beahm, C. F. Weber, T. S. Kress, W. E. Shockley, and S. R. Daish, "Chemistry and Mass Transport of Iodine in Containment," pp. 251-66 in Proc. 2nd CSNI Workshop on Iodine Chemistry in Reactor Safety, Toronto, Canada, June 2-3, 1988 (1989).

E. C. Beahm, C. F. Weber, T. S. Kress, and W. E. Shockley, "Iodine Behavior in Containment," ICHMT Seminar on Fission Product Transport Processes in Reactor Accidents, Dubrovnik, Yugoslavia, May 22-26, 1989.

C. F. Weber, E. C. Beahm, T. S. Kress, S. R. Daish, and W. E. Shockley, "TRENDS: A Code for Modeling Iodine Behavior in Containment During Severe Accidents," Proc. ICHMT Int. Seminar on Heat and Mass Transfer Aspects of Fission Product Releases, Dubrovnik, Yugoslavia, May 22-26, 1989.

W. A. Rhoades, R. L. Childs, and D. T. Ingersoll, Radiation Exposure Inside Reinforced Concrete Buildings at Nagasaki, ORNL/TM-10569, Martin Marietta Energy Systems, May 1989.

J. W. Roddy, R. C. Ashline, O. W. Hermann, C. V. Parks, and J. P. Renier, Multicode Comparison of Selected Source Term Computer Codes, ORNL/CSD/TM-251, Martin Marietta Energy Systems, Oak Ridge National Laboratory, April 1989.

J. O. Johnson and M. B. Emmett, "Initial Verification of the Monte Carlo Adjoint Shielding Code (MASH)," Am. Nucl. Soc. Top. Conf. on Advances in Nuclear Computation and Radiation Shielding, Santa Fe, N. Mex., April 9-13, 1989.

R. G. Alsmiller, F. S. Alsmiller, T. A. Gabriel, O. W. Hermann, and J. M. Barnes, "The High-Energy Transport Code HETCSS," Proc. Workshop on Calorimetry for the Superconducting Super Collider, University of Alabama, Tuscaloosa, Ala., March 13-17, 1989.

A. D. Kelmers, L. B. Shappert, J. W. Roddy, O. W. Hermann, and C. V. Parks, Identification and Evaluation of Radionuclide Generation/Depletion Codes for Potential Use by the Department of Energy's Office of Civilian Radioactive Waste Management, ORNL/TM-10404, Martin Marietta Energy Systems, Oak Ridge National Laboratory, February 1989.