Oak Ridge National Laboratory

Nuclear Engineering Applications Section
1997

  Author(s) / Report Title / Publication Number / Date
K. R. Elam, C. W. Forsberg, C. M. Hopper, and R. Q. Wright, Isotopic Dilution Requirements for 233U Criticality Safety in Processing and Disposal Facilities, ORNL/TM-13524, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, November 1997.
R. M. Westfall,  "Evolution of Cross-Section Data for Criticality Safety Applications," ANS 1997 Winter Meeting, November 16-20, 1997, Albuquerque, New Mexico.  Trans. Am. Nucl. Soc., 77, 229-230 (1997).
C. V. Parks,  "Overview of Validation," ANS 1997 Winter Meeting & Embedded Topical Meetings, November 16-20, 1997, Albuquerque, New Mexico.
S. M. Bowman, B. L. Broadhead, D. F. Hollenbach, and L. M. Petrie,  Joint Report of Foreign Travel to Rez (near Prague), Czech Republic, October 9-18, 1997, ORNL/FTR-6399, November 1997.
N. M. Greene and R. M. Westfall,  "Cross Sections for Criticality Safety Applications," ANS 1997 Winter Meeting, November 16-20, 1997, Albuquerque, New Mexico.   Trans. Am. Nucl. Soc., 77, 227-229 (1997).
M. J. Haire, W. C. Jordan, and R. G. Taylor,  "Storage Array Reflection Considerations," ANS 1997 Winter Meeting, November 16-20, 1997, Albuquerque, New Mexico.   Trans. Am. Nucl. Soc., 77, 222-223 (1997).
B. L. Broadhead,  "Application of Generalized Linear Least-Squares Methodology to Criticality Safety Computations," ANS 1997 Winter Meeting, November 16-20, 1997, Albuquerque, New Mexico.   Trans. Am. Nucl. Soc., 77, 234-235 (1997).
B. L. Broadhead, R. T. Primm III, and S. E. Fisher,  "Strategy for Validating Shielding Methods for Reactor-Based Disposition of Weapons-Grade Plutonium," ANS 1997 Winter Meeting, November 16-20, 1997, Albuquerque, New Mexico.   Trans. Am. Nucl. Soc. 77, 318-319 (1997). [Invited]
R. T. Primm III, B. D. Murphy, and J. B. Knauer, Jr.,  Joint Report of Foreign Travel to SCK*CEN Analytical Laboratory and Belgonucleaire, Brussels, Belgium, October 29-31, 1997, ORNL/FTR-6407, October 1997.
S. Raman, R. L. Walker, J. K. Dickens, and B. D. Murphy, "The US/UK Actinides Experiment at the Dounreay PFR,"  Vol. 2, pp. 1390-1392  in  Proceedings of the International Conference on Future Nuclear Systems: Challenge Towards Second Nuclear Era with Advanced Fuel Cycles, October 5-10, 1997, Pacifico Yokohama, Yokohama, Japan.
D. F. Hollenbach and C. M. Hopper,  "Criticality Safety Considerations for MSRE Fuel Drain Tank Uranium Aggregation," pp. 73-79 in Proceedings of the Topical Meeting on Criticality Safety Challenges in the Next Decade, September 7-12, 1997, Chelan, Washington.
C. M. Hopper and C. V. Parks,  "Potential for and Consequences of Criticality Resulting from Hydrogeochemically Concentrated Fissile Uranium Blended with Soil in Low-Level Waste Disposal Facilities," pp. 73-79 in  Proceedings of the Topical Meeting on Criticality Safety Challenges in the Next Decade, September 7-12, 1997, Chelan, Washington.
C. M. Hopper, R. Q. Wright, K. R. Elam, and C. W. Forsberg, "Isotopic Dilution of U-233 with Depleted Uranium for Criticality Safety in Processing and Disposal," Proceedings of the Topical Meeting on Criticality Safety Challenges in the Next Decade, September 7-12, 1997, Chelan, Washington.
J. J. Lichtenwalter,  "Heterogeneous Reactivity Effects in Medium- and High-Enriched Uranium Metal-Water Systems," Proceedings of the Topical Meeting on Criticality Safety Challenges in the Next Decade, September 7-12, 1997, Chelan, Washington.
D. E. Cabrilla and R. M. Westfall, "Meeting the Challenge: Assuring Adequate Criticality Predictability," in pp. 3–8 in Proceedings Criticality Safety Challenges in the Next Decade Topical Meeting of the Nuclear Criticality Safety Division, September 7 – 12, 1997, Chelan, Washington.
B. D. Murphy,  Characteristics of Spent Fuel From Plutonium Disposition Reactors. Vol. 3: A Westinghouse Pressurized-Water Reactor Design,  ORNL/TM-13170/V3, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, July 1997.
E. S. Glouchkov, C. M. Hopper, W. C. Jordan, and R. G.  Taylor,  Report of Foreign Travel to Japan, ORNL/FTR-6249, July  1997.
M. D. DeHart and R. M. Westfall,  Report of Foreign Travel to Paris, France, July 7-13, 1997, ORNL/FTR-6250.
S. M. Bowman, M. D. DeHart, and C. V. Parks,  "USLSTATS: Computerized Statistical Methods for Determination of Bias and Subcritical Limits," ANS 1997 Annual Meeting, June 1-5, 1997, Orlando, Florida.   Trans. Am. Nucl. Soc., 76, 238-241, (1997).
L. Petrie, D. K. Parsons, and G. D. Spriggs,  "KENO Lifetimes," ANS 1997 Annual Meeting, June 1-5, 1997, Orlando, Florida.   Trans. Am. Nucl. Soc., 76, 367-368 (1997).
M. D. DeHart and C. V. Parks,  "SCALE Depletion Calculations Based on Two-Dimensional PWR Assembly Flux Solutions," ANS 1997 Annual Meeting, June 1-5, 1997, Orlando, Florida.   Trans. Am. Nucl. Soc., 76, 53-57 (1997).
M. E. Dunn, C. L. Bentley, S. Goluoglu, R. E. Pevey, H. L. Dodds, and L. M. Petrie, "Continuous-Energy Methods Development for the Monte Carlo Code KENO V.a," ANS 1997 Annual Meeting, June 1-5, 1997, Orlando, Florida.   Trans. Am. Nucl. Soc. 76, 234-235 (1997).
L. E. Toran, C. M. Hopper, M. T. Naney, C. V. Parks, J. F. McCarthy, B. L. Broadhead, and V. A. Colten-Bradley,  The Potential for Criticality Following Disposal of Uranium at Low- Level Waste Facilities. Volume 1: Uranium Blended with Soil, NUREG/CR-6505, Vol. 1 (ORNL/TM-13323/V1), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, June 1997.
H. R. Dyer and C. V. Parks, Recommendations for Preparing the Criticality Safety Evaluation of Transportation Packages, NUREG/CR-5661 (ORNL/TM-11936), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, April 1997.
B. L. Broadhead, C. M. Hopper, R. L. Childs, and J. S. Tang,  An Updated Nuclear Criticality Slide Rule. Volume 1: Technical Basis, NUREG/CR-6504, Vol. 1 (ORNL/TM-13322/V1), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, April 1997.
S. M. Bowman, et al.,  SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, Vols. I-III, NUREG/CR-0200, Rev. 5 (ORNL/NUREG/CSD-2/R5), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, March 1997.
J. J. Lichtenwalter, S. M. Bowman, and M. D. DeHart,  Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages,  NUREG/CR-6361 (ORNL/TM-13211), U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, March 1997.
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," Nucl. Tech., 117, 206-222, February 1997.
C. V. Parks, Report of Foreign Travel to Vienna, Austria, January 11-18, 1997, ORNL/FTR-6074, February 1997.
R. Raman, R. L. Walker, and B. D. Murphy, "Actinide Behavior in the US/UK Actinides Experiment at the Dounreay PFR," pp. 1326-1328 in  Proceedings of the Nuclear Data for Science and Technology, G. Reffo, A. Ventura, and C. Grandi (Eds.), SIF, Bologna, 1997.


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