P. B. Fox
PUBLICATIONS
2008
D. E. Mueller, K. R. Elam, and P. B. Fox, Evaluation of the French Haut Taux de Combustion (HTC) Critical Experiment Data, NUREG/CR-6979 (ORNL/TM-2007/083), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2008.2007
G. Radulescu, D. E. Mueller, S. Goluoglu, D. F. Hollenbach, and P. B. Fox, Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel, ORNL/TM-2007/127, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2007. <2005
D. F. Hollenbach and P. B. Fox, "Benchmark Analysis of the SCALE 5 Versions of the KENO-VI and CENTRM Codes," presented at the 2005 NCSD Topical Meeting, September 19-22, 2005, Knoxville, TN.
P. B. Fox, L. M. Petrie, Jr., and C. M. Hopper, Minimum Critical Values Study, ORNL/TM-2003/211, Oak Ridge National Laboratory, Oak Ridge, Tenn., July 2005.
P. B. Fox and D. F. Hollenbach, KENO-VI Validation, ORNL/TM-2004/60, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2005.
D. F. Hollenbach and P. B. Fox, CENTRM Validation, ORNL/TM-2004/66, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2005.
M. E. Dunn, P. B. Fox, N. M. Greene, and L. M. Petrie, "ENDF/B-VI Library Generation and Testing for the SCALE Code System," Trans. Am. Nucl. Soc. 92, 758-759 (2005).2002
P. B. Fox and L. M. Petrie, Validation and Comparison of KENO V.a and KENO-VI, ORNL/TM-2001/110, UT-Battelle, LLC, Oak Ridge National Laboratory, May 2002.
2001
D. F. Hollenbach, L. M. Petrie, P. B. Fox, and K. R. Elam, “SCALE 5: New Cross-Section Processing Features and Capabilities,” 35390.pdf in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11–15, 2001, Reno, NV. [ANS Order No.: 700284; ISBN: 0-89448-659-4]
2000
D. F. Hollenbach and P. B. Fox, Neutronics Benchmarks of Mixed-Oxide Fuels Using the SCALE/CENTRM Sequence, ORNL/TM-1999/299, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, February 2000.
B. T. Rearden, C. M. Hopper, K. R. Elam, B. L. Broadhead, and P. B. Fox, “Prototypic Applications of Sensitivity and Uncertainty Analysis for Experiment Needs,” in Proc. of ANS/ENS 2000 International Winter Meeting and Embedded Topical Meetings, November 12–16, 2000, Washington, D.C., Trans. Am. Nucl. Soc.83, 103–107, 2000.
S. M. Bowman, B. L. Broadhead, C. B. Bryan, J. A. Bucholz, K. W. Childs, A. L. Edwards, M. B. Emmett, P. B. Fox, S. K. Fraley, G. E. Gilels, N. M. Greene, O. W. Hermann, T. J. Hoffman, D. F. Hollenbach, W. C. Jordan, J. R. Knight, N. F. Landers, L. C. Leal, K. Lucius, C. V. Parks, L. M. Petrie, J. C. Ryman, J. S. Tang, J. C. Turner, J. T. West, R. M. Westfall, and P. T. Williams, SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2R6), Vols. I, II, III, May 2000. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-545.
L. M. Petrie, P. B. Fox, and K. Lucius, “Standard Composition Library,” Vol. III, Sect. M8 of SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, NUREG/CR-0200, Version 4.4a, Rev. 6 (ORNL/NUREG/CSD-2R6), Vols. I, II, and III, May 2000. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-545.
1999
M. E. Dunn and P. B. Fox, Criticality Safety Scoping Study for the Transport of Weapons-Grade Mixed-Oxide Fuel Using the MO-1 Shipping Package, ORNL/TM-13741, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, May 1999.
1997
SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, NUREG/CR-0200, Version 4.3, Rev. 5 (ORNL/NUREG/CSD-2R5), Vols. I, II, and III, March 1997. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-545.
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), prepared for the U.S. Nuclear Regulatory Commission by the Oak Ridge National Laboratory, Oak Ridge, Tenn., March 1995.
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. Int. Top. Meet. on Safety Margins in Criticality Safety, November 26–30, 1989, San Francisco, CA (1989).
1987
P. B. Fox and M. Yatabe, “The New Interactive CESAR,” American Nuclear Society Winter Meeting, November 15–19, 1987, Los Angeles, CA. Trans. Am. Nucl. Soc., 55, 385, 1987.
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, November 1985.
1977
N. F. Cross, R. M. Westfall, K. R. Turnbull, P. B. Fox, “Validation of Criticality Safety Broad Group Library Using Uranium Systems,” Trans. Am. Nucl. Soc. 27, 406–407 (1977).