Critical Dimensions of Systems Containing 235U, 239Pu, and 233U
0. H.C. Paxton and N. L. Pruvost, “Critical Dimensions of Systems Containing 235U, 239Pu, and 233U, 1986 Revision,” Los Alamos National Laboratory report LA-10860-MS (July 1987).
1. H. C. Paxton, J. T. Thomas, Dixon Callihan, and E. B. Johnson, “Critical Dimensions of Systems Containing U235, Pu239, and U233,” Los Alamos Scientific Laboratory and Oak Ridge National Laboratory report TID-7028 (June 1964).
2. J. T. Thomas, Ed., “Nuclear Safety Guide TID-7016,” U. S. Nuclear Regulatory Commission report NUREG/CR-0095 (ORNL/NUREG/CSD-6) (June 1978).
3. “Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors,” ANSI/ANS-8.1-1983 (Revision of ANSI/N16.1-1975) (American National Standards Institute, Inc., New York, 1983).
4. H. K. Clark, “Subcritical Limits for Plutonium Systems,” Nucl. Sci. Eng. 79, 65-84 (1981).
5. H. K. Clark, “Subcritical Limits for Uranium-235 Systems,” Nucl. Sci. Eng. 81, 351-378 (1982).
6. H. K. Clark, “Subcritical Limits for Uranium-233 Systems,” Nucl. Sci. Eng. 81, 379-395 (1982).
7. H. K. Clark, “Handbook of Nuclear Safety,” Savannah River Laboratory report DP-532 (January 1961). F. Abbey, “Manual of Criticality Data, Parts 1, 2, 3,” AHSB(s) Handbook 5, UKAEA Health and Safety Branch (1967). “Guide de Criticite, Parts I, II, III,” (in French) CEA-R3114, Commissariat a l’Energie Atomique, Saclay (1967). B. G. Dubovskiy et al., “Critical Parameters of Fissionable Materials Systems and Nuclear Safety (A Handbook),” Russian Translation JPRS:42,322, Clearing House for Federal Scientific and Technical Information (1967). R. D. Carter, G. R. Kiel, and K. R. Ridgway, “Criticality Handbook, Vols. I, II, III,” Atlantic Richfield Hanford Co. report ARH-600 (1968).
8. H. F. Henry, A. J. Mallett, C. E. Newlon, and W. A. Pryor, “Criticality Data and Nuclear Safety Guide Applicable to the Oak Ridge Gaseous Diffusion Plant,” Union Carbide Nuclear Company, K-25 Plant report K-1019 (5th Rev.) (May 1959). E. D. Clayton, “Nuclear Safety in Chemical and Metallurgical Processing of Plutonium,” Hanford Atomic Products report HW-68929 (April 1961).
9. D. Callihan, “Experiments for Criticality Control,” in Criticality Control in Chemical and Metallurgical Plant, Karlsruhe Symposium, 1961 (Organisation for Economic Cooperation and Development, European Nuclear Energy Agency, Paris, 1961), pp. 589-614.
10. G. E. Hansen and W. H. Roach, “Six and Sixteen Group Cross Sections for Fast and Intermediate Critical Assemblies,” Los Alamos Scientific Laboratory report LAMS-2543 (November 1961).
11. B. G. Carlson, C. Lee, and W. Worlton, “The DSN and TDC Neutron Transport Codes,” Los Alamos Scientific Laboratory reports LAMS-2346 and LAMS-2346, Appendix I (October 1959).
12. R. D. O’Dell, F. W. Brinkley, Jr., and D. R. Marr, “User’s Manual for ONEDANT: A Code Package for One-Dimensional, Diffusion-Accelerated, Neutral-Particle Transport,” Los Alamos National Laboratory report LA-9184-M (February 1982).
13. R. E. Alcouffe, F. W. Brinkley, D. R. Marr, and R. D. O’Dell, “User’s Guide for TWODANT: A Code Package for Two-Dimensional, Diffusion-Accelerated, Neutral-Particle Transport,” Los Alamos National Laboratory report LA-10049-M, Rev. 1 (October 1984).
14. W. R. Stratton, “Criticality Data and Factors Affecting Criticality of Single Homogeneous Units,” Los Alamos Scientific Laboratory report LA-3612 (September 1967).
15. J. F. Briesmeister, Ed., “MCNP-A General Monte Carlo Code for Neutron and Photon Transport, Version 3A,” Los Alamos National Laboratory report LA-7396-M, Rev. 2, Manual (September 1986).
16. H. C. Paxton, “Fast Critical Experiments,” in Progress in Nuclear Energy (Pergamon Press, Ltd., 1981), Vol. 7, pp. 151-174.
17. Roy Reider, “An Early History of Criticality Safety,” Los Alamos Scientific Laboratory report LA-4671 (May 1971).
18. Los Alamos Scientific Laboratory of the University of California, “An Enriched Homogeneous Nuclear Reactor,” Rev. Sci. Inst. 22, 489-499 (1951); also L. D. P. King, “Water Boilers,” Los Alamos Scientific Laboratory report LA-1034, Chapter 4 (December 1947).
19. H. D. Smyth, Atomic Energy for Military Purposes (Princeton University Press, Princeton, New Jersey, 1945), pp. 98, 143.
20. H. C. Paxton, “Los Alamos Critical Mass Data,” Los Alamos Scientific Laboratory report LA-3067-MS, Rev. (December 1975).
21. A. H. Snell, “Critical Experiments on Fluorinated and Hydrogenated Mixtures Containing Enriched Uranium,” Monsanto Clinton Laboratories report MonP-48 (November 1945).
22. C. K. Beck, A. D. Callihan, and R. L. Murray, “Critical Mass Studies, Part I,” Carbide and Carbon Chemicals Corporation report A-4716 (June 1947).
23. C. K. Beck, A. D. Callihan, and R. L. Murray, “Critical Mass Studies, Part II,” Carbide and Carbon Chemicals Corporation report K-126 (January 1948).
24. R. Caizergues, E. Deilgat, P. Lécorché, L. Maubert, and H. Revol, “Criticality of Liquid Mixtures of Highly 235U-Enriched Uranium Hexafluoride and Hydrofluoric Acid,” (translation) Union Carbide Corporation report Y-CDC-9 (May 1971).
25. W. R. Stratton, “A Review of Criticality Accidents,” Los Alamos Scientific Laboratory report. LA-3611 (1967).
26. F. E. Kruesi, J. O. Erkman, and D. D. Lanning, “Critical Mass Studies of Plutonium Solutions,” Hanford Atomic Products Operation report HW-24514 (Del.) (May 1952).
27. R. C. Lloyd, E. D. Clayton, and W. A. Reardon, “Operating Experience in the Hanford Plutonium Critical Mass Facility,” Trans. Am. Nucl. Soc. 5, 76, 77 (1962).
28. J. G. Walford and A. F. Thomas, “The Equipment and Methods Used in British Criticality Laboratories,” in Criticality Control in Chemical and Metallurgical Plant, Karlsruhe Symposium, 1961 (Organisation for Economic Cooperation and Development, European Nuclear Energy Agency, Paris, 1961), pp. 553-588.
29. J. Carothers, “Hazards Summary Report for the LRL Critical Facility,” Lawrence Radiation Laboratory report UCRL-6220 (March 1960).
30. P. R. Lécorché, “Critical Mass Laboratory Program in France,” Trans. Am. Nucl. Soc. 16, 158, 159 (1973).
31. C. L. Schuske, “Experimental Programs at the Dow Rocky Flats Nuclear Safety Laboratory,” Trans. Am. Nucl. Soc. 16, 157, 158 (1973).
32. C. K. Beck, A. D. Callihan, J. W. Morfitt, and R. L. Murray, “Critical Mass Studies, Part III,” Carbide and Carbon Chemicals Corporation report K-343 (April 1949).
33. J. K. Fox, L. W. Gilley, and D. Callihan, “Critical Mass Studies, Part IX. Aqueous U235 Solutions,” Oak Ridge National Laboratory report ORNL-2367 (March 1958).
34. J. K. Fox, L. W. Gilley, and J. H. Marable, “Critical Parameters of a Proton-Moderated and Proton-Reflected Slab of U235,” Nucl. Sci. Eng. 3, 694-697 (1958).
35. J. T. Mihalczo and J. J. Lynn, “Neutron Multiplication Experiments with Enriched Uranium Metal in Slab Geometry,” Oak Ridge National Laboratory report ORNL-CF-61-4-33 (April 1961).
36. J. T. Mihalczo, “Graphite and Polyethylene Reflected Uranium Metal Cylinders and Annuli,” Union Carbide Corporation, Nuclear Division report Y-DR-81 (April 1972).
37. G. E. Hansen, H. C. Paxton, and D. P. Wood, “Critical Plutonium and Enriched-Uranium-Metal Cylinders of Extreme Shape,” Nucl. Sci. Eng. 8, 570-577 (1960).
38. E. C. Mallary, “Oralloy Cylindrical Shape Factor and Critical Mass Measurements in Graphite, Paraffin, and Water Tampers,” Los Alamos Scientific Laboratory report LA-1305 (October 1951).
39. G. E. Hansen, D. P. Wood, and B. Pena, “Reflector Savings of Moderating Materials on Large-Diameter U(93.2) Slabs,” Los Alamos Scientific Laboratory report LAMS-2744 (October 1962).
40. J. K. Fox, L. W. Gilley, and E. R. Rohrer, “Critical Mass Studies, Part VIII. Aqueous Solutions of U233,” Oak Ridge National Laboratory report ORNL-2143 (September 1959).
41. F. A. Kloverstrom, “Spherical and Cylindrical Plutonium Critical Masses,” University of California Radiation Laboratory report UCRL-4957 (September 1957).
42. C. L. Schuske, M. G. Arthur, and D. F. Smith, “Criticality Measurements on Plutonium Metal Preliminary to the Design of a Melting Crucible,” Dow Chemical Co., Rocky Flats Plant report RFP-63 (June 1956).
43. R. C. Lane, “Measurements of the Critical Parameters of Under-Moderated Uranium-Hydrogen Mixtures at Intermediate Enrichment,” in Proceedings of the Symposium Criticality Control of Fissile Materials, Stockholm, 1-5 November 1965 (International Atomic Energy Agency, Vienna, 1966) pp. 177-191.
44. A. D. Callihan, D. F. Cronin, J. K. Fox, and J. W. Morfitt, “Critical Mass Studies, Part V,” Carbide and Carbon Chemicals Corp., K-25 Plant report K-643 (June 1950).
45. G. A. Linenberger, J. D. Orndoff, and H. C. Paxton, “Enriched-Uranium Hydride Critical Assemblies,” Nucl. Sci. Eng. 7, 44-57 (1960).
46. L. E. Hansen and E. D. Clayton, “Criticality of Plutonium Compounds in the Under-Moderated Range, H/Pu ≤ 20,” Nucl. Appl. 3, 481-487 (1967).
47. J. S. Johnson and K. A. Kraus, “Density and Refractive Index of Uranyl Fluoride Solutions,” J. Am. Chem. Soc. 75, 4594-4595 (1953).
48. J. T. Thomas, J. K. Fox, and Dixon Callihan, “A Direct Comparison of Some Nuclear Properties of U-233 and U-235,” Nucl. Sci. Eng. 1, 20-32 (1956).
49. J. T. Thomas, “Parameters for Two Group Analysis of Critical Experiments with Water Reflected Spheres Of UO2F2 Aqueous Solutions,” Oak Ridge National Laboratory report ORNL-CF-56-8-201 (August 1956).
50. J. K. Fox, L. W. Gilley, R. Gwin, and J. T. Thomas, “Critical Parameters of Uranium Solutions in Simple Geometry,” in “Neutron Physics Division Annual Progress Report for Period Ending September 1, 1958,” Oak Ridge National Laboratory report ORNL-2609 (October 1958), p.42.
51. R. Gwin and D. W. Magnuson, “The Measurement of Eta and Other Nuclear Properties of U233 and U235 in Critical Aqueous Solutions,” Nucl. Sci. Eng. 12, 364-380 (1962).
52. R. H. Masterson, J. D. White, and T. J. Powell, “The Limiting Critical Concentrations for Pu239 and U235 in Aqueous Solutions,” Hanford Atomic Products Operation report HW-77089 (March 1963).
53. R. E. Peterson and G. A. Newby, “An Unreflected U-235 Critical Assembly,” Nucl. Sci. Eng.1, 112-125 (1956).
54. C. C. Byers, J. J. Koelling, G. E. Hansen, D. R. Smith, and H. R. Dyer, “Critical Measurements of a Water-Reflected Enriched Uranium Sphere,” Trans. Am. Nucl. Soc. 27, 412-413 (1977).
55. J. T. Mihalczo and J. J. Lynn, “Critical Parameters of Bare and Reflected 93.4 wt% U235-Enriched Uranium Metal Slabs,” in “Neutron Physics Division Annual Progress Report for Period Ending September 1, 1960,” Oak Ridge National Laboratory report ORNL-3016 (December 1960), pp. 73-76.
56. H. R. Ralston, “Critical Masses of Spherical Systems of Oralloy Reflected in Beryllium,” University of California Radiation Laboratory report UCRL-4975 (October 1957).
57. R. E. Donaldson and W. K. Brown, “Critical-Mass Determinations of Lead-Reflected Systems,” University of California Radiation Laboratory report UCRL-5255 (June 1958).
58. D. W. Magnuson, “Critical Experiments with Enriched Uranium Dioxide,” Union Carbide Corporation, Y-12 Plant report Y-DR-120 (November 1973).
59. J. G. Bruna, J. P. Brunet, R. Caizergues, C. Clouet d’Orval, and P. Verriere, “Results of Homogeneous Critical Experiments Carried Out with 239Pu, 235U, and 233U,” (in French) in Proceedings of the Symposium Criticality Control of Fissile Materials, Stockholm, 1-5 November 1965 (International Atomic Energy Agency, Vienna, 1966), pp. 235-248.
60. P. Lécorché and R. L. Seale, “A Review of the Experiments Performed to Determine the Radiological Consequences of a Criticality Accident,” Oak Ridge Criticality Data Center report Y-CDC-12 (November 1973).
61. B. G. Dubovskii, A. V. Kamaev, V. V. Orlov, C. M. Vladykov, V. N. Gurin, F. M. Kuznetsov, V. P. Kochergin, I. P. Markelov, G. A. Popov, and V. J. Sviridenko, “The Critical Parameters of Aqueous Solutions Of UO2(NO3)2 and Nuclear Safety,” in Proceedings of the Third International Conference on the Peaceful Uses of Atomic Energy, Geneva, 1964 (United Nations, New York, 1965), Vol. 13, pp. 254-263.
62. D. F. Cronin, “Critical Mass Studies, Part X, Uranium of Intermediate Enrichment,” Oak Ridge National Laboratory report ORNL-2968 (October 1960).
63. S. J. Raffety and J. T. Mihalczo, “Homogeneous Critical Assemblies of 2 and 3% Uranium-235-Enriched Uranium in Paraffin,” Nucl. Sci. Eng. 48, 433-443 (1972).
64. J. C. Smith, A. V. Parker, J. G. Walford, and C. White, “Criticality of 30% Enriched Uranium Solutions in Cylindrical Geometry,” Dounreay Experimental Reactor Establishment report DEG-Memo-663 (March 1960).
65. R. E. Carter, J. C. Hinton, L. D. P. King, and R. E. Schreiber, “Water Tamper Measurements,” Los Alamos Scientific Laboratory report LA-241 (March 1945).
66. E. B. Johnson, “Criticality of a Sphere of U(4.98)UO2F2 Solution,” in “Neutron Physics Division Annual Progress Report for Period Ending May 31, 1966,” Oak Ridge National Laboratory report ORNL-3973 (September 1966), pp. 14, 15.
67. E. B. Johnson, “Critical Lattices of U(4.89), Rods in Water and in Aqueous Boron Solution,” Trans. Am. Nucl. Soc. 11, 675 (1968).
68. C. G. Chezem and R. G. Steinke, “Low-Enrichment Uranium-Metal Exponential Experiments,” Nucl. Sci. Eng. 31, 549,550 (1968).
69. J. J. Neuer, “Critical Assembly of Uranium Metal at an Average U235 Concentration of 16-1/4%,” Los Alamos Scientific Laboratory report LA-2085 (January 1957).
70. R. H. White, “Topsy, A Remotely Controlled Critical Assembly Machine,” Nucl. Sci. Eng. 1, 53-61 (1956).
71. H. C. Paxton, “Bare Critical Assemblies of Oralloy at Intermediate Concentrations of U235,” Los Alamos Scientific Laboratory report LA-1671 (July 1954).
72. Darrouzet, J. P. Chandat, E. A. Fischer, G. Ingram, J. E. Sanders, and W. Scholtyssek, “Studies of Unit k Lattices in Metallic Uranium Assemblies Zebra 8H, Sneak 8, Ermine and Harmonie,” in Proc. Int. Symposium on Physics of Fast Reactors, Tokyo, October 16-19, 1973 (Power Reactor and Nuclear Fuel Development Corporation, Tokyo), Vol. I, pp. 537-570.
73. E. B. Johnson, “Critical Parameters of U(1.95) Metal Cylindrical Annuli,” Trans. Am. Nucl. Soc. 9, 185,186 (1966). E. B. Johnson, “Criticality of U(3.85) Rods and Cylindrical Annuli in Water,” Trans. Am. Nucl. Soc. 13, 379 (1970).
74. E. B. Johnson and L. M. Petrie, “The Criticality of Large Uranium Metal Units of Low Enrichment in 235U,” Oak Ridge National Laboratory report ORNL-6310 (1987).
75. J. C. Hoogterp, “Unreflected Plexiglas-Graphite-Uranium Critical Measurements,” Trans. Am. Nucl. Soc. 11, 389,390 (1968).
76. H. Kouts, G. Price, K. Downes, R. Sher, and V. Walsh, “Exponential Experiments with Slightly Enriched Uranium Rods in Ordinary Water,” in Proceedings of the First International Conference on the Peaceful Uses of Atomic Energy, Geneva, 1955 (United Nations, New York, 1956), Vol. 5, pp. 183-202.
77. H. Kouts, R. Sher, J. R. Brown, D. Klein, S. Stein, R. L. Hellens, H. Arnold, R. M. Ball, and P. W. Davison, “Physics of Slightly Enriched, Normal Water Lattices (Theory and Experiment),” in Proceedings of the Second International Conference on the Peaceful Uses of Atomic Energy, Geneva, 1957 (United Nations, New York, 1958), Vol. 12, pp. 446-482.
78. E. B. Johnson, “Criticality of Uranium of Low Enrichment in Water,” Trans. Am. Nucl. Soc. 12, 336 (1969).
79. C. R. Richey, R. C. Lloyd, and E. D. Clayton, “Criticality of Slightly Enriched Uranium in Water-Moderated Lattices,” Nucl. Sci. Eng. 21, 217-226 (1965).
80. W. B. Rogers, Jr., and F. E. Kinard, “Material Buckling and Critical Masses of Uranium Rods Containing 3 wt% U235 in H2O,” Nucl. Sci. Eng. 20, 266-271 (1964).
81. J. C. Manaranche, D. Mangin, L. Maubert, G. Colomb, and G. Poullot, “Critical Experiments with Lattices of 4.75 wt% 235U-Enriched UO2 Rods in Water,” Nucl. Sci. Eng. 71, 154-163 (1979).
82. J. C. Hoogterp, “Critical Masses of Oralloy Lattices Immersed in Water,” Los Alamos Scientific Laboratory report LA-2026 (March 1957).
83. J. K. Fox and L. W. Gilley, “Critical Experiments with Arrays of ORR and BSR Fuel Elements,” in “Neutron Physics Division Annual Progress Report for Period Ending September 1, 1958,” Oak Ridge National Laboratory report ORNL-2609 (October 1958), pp. 34-36.
84. E. B. Johnson and R. K. Reedy, Jr., “Critical Experiments with SPERT-D Fuel Elements,” Oak Ridge National Laboratory report ORNL-TM-1207 (July 1965).
85. A. Goodwin, Jr., G. H. Bidinger, and C. L. Schuske, “Criticality Studies of Enriched Uranium Metal in UO2(NO3)2 Solutions,” Dow Chemical Co., Rocky Flats Plant report RFP-182 (July 1960).
86. C. L. Schuske, M. G. Arthur, and D. F. Smith, “Neutron Multiplication Measurements on Oralloy Slabs Immersed in Solutions,” Dow Chemical Co., Rocky Flats Plant report RFP-66 (August 1956).
87. C. L. Schuske, M. G. Arthur, and D. F. Smith, “Neutron Multiplication Measurements on Oralloy Slabs Immersed in Solution, Part II,” Dow Chemical Co., Rocky Flats Plant report RFP-69 (October 1956).
88. W. A. Reardon and J. D. White, “Calculations of Criticality Properties of Plutonium Nitrate Systems,” Hanford Atomic Products Operation report HW-72586 (January 1962), pp. 66-78.
89. C. C. Horton and J. D. McCullen, “Plutonium-Water Critical Assemblies,” in Proceedings of the First International Conference on the Peaceful Uses of Atomic Energy, Geneva, 1955 (United Nations, New York, 1956), Vol. 5, pp. 156-161.
90. J. Bruna, J. P. Brunet, R. Caizergues, C. Clouet d’Orval, J. Kremser, J. LeClerc, and P. Verriere, “Criticality Experiment on a Plutonium Solution,” (in French) Commissariat a l’Energie Atomique report CEA-2274, Centre d’Etudes Nucleaires, Saclay (1963).
91. M. F. Ithurralde, J. Kremser, J. LeClerc, C. Lombard, J. Moreau, and C. Robin, “Interpretation of Criticality Experiments on Homogeneous Solutions of Plutonium and Uranium,” (in French) Commissariat a l’Energie Atomique report CEA-R-2488 (1964).
92. D. Breton, P. Lécorché, and C. Clouet d’Orval, “Criticality Studies,” (in French) in Proceedings of the Third United Nations International Conference on the Peaceful Uses of Atomic Energy, Geneva, 1964 (United Nations, New York, 1965), Vol. 13, pp. 234-242.
93. R. C. Lloyd, C. R. Richey, E. D. Clayton, and D. R. Skeen, “Criticality Studies with Plutonium Solutions,” Nucl. Sci. Eng. 25, 165-173 (1966).
94. R. C. Lloyd, E. D. Clayton, L. E. Hansen, and S. R. Bierman, “Criticality of Plutonium Nitrate Solutions in Slab Geometry,” Nucl. Technol. 18, 225-230 (1973).
95. D. R. Smith and W. U. Geer, “Critical Mass of a Water-Reflected Plutonium Sphere,” Nucl. Appl. Technol. 7, 405-408 (1969).
96. R. C. Lloyd, R. A. Libby, and E. D. Clayton, “The Measurement of Eta and the Limiting Critical Concentration of 239Pu, in Critical Aqueous Solutions,” Nucl. Sci. Eng. 82, 325-331 (1982).
97. G. Colomb, D. Mangin, and L. Maubert, “Criticality of Plutonium Nitrate Solutions (19% 240Pu),” (in French) Commissariat a l’Energie Atomique report CEA-N-1898 (September 1976).
98. R. C. Lloyd and E. D. Clayton, “The Criticality of High Burnup Plutonium,” Nucl. Sci. Eng. 52, 73-75 (1973).
99. C. R. Richey, J. D. White, E. D. Clayton, and R. C. Lloyd, “Criticality of Homogeneous Plutonium Oxide-Plastic Compacts at H:Pu = 15,” Nucl. Sci. Eng. 23, 150-158 (1965).
100. S. R. Bierman, L. E. Hansen, R. C. Lloyd, and E. D. Clayton, “Critical Experiments with Homogeneous PuO2-Polystyrene at 5 H/Pu,” Nucl. Appl. 6, 23-26 (1969).
101. S. R. Bierman and E. D. Clayton, “Critical Experiments with Homogeneous PUO2-Polystyrene at 50 H/Pu,” Nucl. Technol. 15, 5-13 (1972).
102. S. R. Bierman and E. D. Clayton, “Critical Experiments with Unmoderated Plutonium Oxide,” Nucl. Technol. 11, 185-190 (1971).
103. S. R. Bierman, E. D. Clayton, and L. E. Hansen, “Critical Experiments with Homogeneous Mixtures of Plutonium and Uranium Oxides Containing 8, 15, and 30 wt% Plutonium,” Nucl. Sci. Eng. 50, 115-126 (1973).
104. R. C. Lloyd, S. R. Bierman, and E. D. Clayton, “Criticality of Plutonium-Uranium Mixtures Containing 5 to 8 wt% Plutonium,” Nucl. Sci. Eng. 55, 51-57 (1974).
105. S. R. Bierman and E. D. Clayton, “Critical Experiments with Low-Moderated Homogeneous Mixtures of Plutonium and Uranium Oxides Containing 8, 15, and 30 wt% Plutonium,” Nucl. Sci. Eng. 61, 370-376 (1976).
106. R. C. Lloyd and E. D. Clayton, “Criticality of Plutonium-Uranium Nitrate Solutions,” Nucl. Sci. Eng. 60, 143-146 (1976).
107. R. C. Lane and O. J. E. Perkins, “The Measurement of the Critical Size of a Homogeneous Mixture of Plutonium and Natural Uranium Oxides with Polythene,” United Kingdom Atomic Energy Authority report AWRE 0 32/68, Aldermaston (July 1968).
108. R. C. Lane and C. Parker, “Measurement of the Critical Size of Solutions of Plutonium and Natural Uranium Nitrates with Pu/U = 0.3,” United Kingdom Ministry of Defense report AWRE 0 58/73, Aldermaston (December 1973).
109. E. D. Clayton, H. K. Clark, D. W. Magnuson, J. H. Chalmers, Gordon Walker, N. Ketzlach, Ryohei Kiyose, C. L. Brown, D. R. Smith, and R. Artigas, “Basis for Subcritical Limits in Proposed Criticality Safety Standard for Mixed Oxides,” Nucl. Technol. 35, 97-111 (1977). E. D. Clayton, H. K. Clark, Gordon Walker, and R. A. Libby, “Basis for Extending Limits in ANSI Standard for Mixed Oxides to Heterogeneous Systems,” Nucl Technol. 75, 225-229 (November 1986).
110. “Nuclear Criticality Control and Safety of Plutonium-Uranium Fuel Mixtures Outside Reactors,” ANSI/ANS-8.12-1987 (American National Standards Institute, Inc., New York, 1987).
111. V. I. Neeley, R. C. Lloyd, and E. D. Clayton, “Neutron Multiplication Measurements with Pu-Al Alloy Rods in Light Water,” Hanford Atomic Products Operation report HW-70944 (August 1961).
112. S. R. Bierman, B. M. Durst, E. D. Clayton, R. I. Scherpelz, and H. T. Kerr, “Critical Experiment with Fast Test Reactor Fuel Pins in Water,” Nucl. Technol. 44, 141-151 (1979).
113. J. T. Thomas, “Critical Experiments with Aqueous Solutions Of 235UO2(NO3)2,” in “Neutron Physics Division Annual Progress Report for Period Ending May 31, 1968,” Oak Ridge National Laboratory report ORNL-4280 (October 1968), pp. 53-55.
114. W. E. Converse, R. C. Lloyd, E. D. Clayton, and W. A. Yuill, “Critical Experiments Using High-Enriched Uranyl Nitrate with Cadmium Absorber,” Trans. Am. Nucl. Soc. 32, 328-330 (1979).
115. E. B. Johnson, “The Criticality of Heterogeneous Lattices of Experimental Beryllium Oxide Reactor Fuel Pins in Water and in Aqueous Solutions Containing Boron and Uranyl Nitrate,” Oak Ridge National Laboratory report ORNL/ENG-2 (July 1976).
116. V. I. Neeley, J. A. Berberet, and R. H. Masterson, “k∞ of Three Weight Percent U235 Enriched UO3 and UO2(NO3)2 Hydrogenous Systems,” Hanford Atomic Products Operation report HW-66882 (September 1961).
117. J. T. Mihalczo and V. I. Neeley, “The Infinite Neutron Multiplication Constant of Homogeneous Hydrogen-Moderated 2.0 wt% U235-Enriched Uranium,” Nucl. Sci. Eng. 13, 6-11 (1962).
118. H. E. Handler, “Measurement of Multiplication Constant for Slightly Enriched Homogeneous UO3-Water Mixtures and Minimum Enrichment for Criticality,” Hanford Atomic Products Operation report HW-70310 (August 1961).
119. R. C. Lloyd, E. D. Clayton, and L. E. Hansen, “Criticality of Plutonium Nitrate Solution Containing Soluble Gadolinium,” Nucl. Sci. Eng. 48, 300-304 (1972).
120. R. C. Lloyd and E. D. Clayton, “Criticality of Plutonium-Uranium Nitrate Solutions,” Nucl. Sci. Eng. 60, 143-146 (1976).
121. R. C. Lloyd, S. R. Bierman, and E. D. Clayton, “Criticality of Plutonium Nitrate Solutions Containing Borated Raschig Rings,” Nucl. Sci. Eng. 50, 127-134 (1973).
122. S. R. Bierman and E. D. Clayton, “Critical Experiments to Measure the Neutron Poisoning Effects of Copper and Copper-Cadmium Plates,” Nucl. Sci. Eng. 55, 58-66 (1974).
123. S. R. Bierman, B. M. Durst, and E. D. Clayton, “Critical Experiments Measuring the Reactivity Worths of Materials Commonly Encountered as Fixed Neutron Absorbers,” Nucl. Sci. Eng. 65, 41-48 (1978).
124. J. T. Thomas, J. K. Fox, and E. B. Johnson, “Critical Mass Studies, Part XIII. Borosilicate Glass Raschig Rings in Aqueous Uranyl Nitrate Solutions,” Oak Ridge National Laboratory report ORNL-TM-499 (February 1963).
125. G. H. Bidinger, C. L. Schuske, and D. F. Smith, “Nuclear Safety Experiments on Plutonium and Enriched Uranium Hydrogen Moderated Assemblies Containing Boron,” Dow Chemical Co., Rocky Flats Plant report RFP-201 (October 1960).
126. C. L. Schuske and G. H. Bidinger, “Nuclear Safety Measurements on Systems Containing Boron and Enriched Uranium,” Dow Chemical Co., Rocky Flats Plant report RFP-246 (October 1961).
127. J. K. Fox and L. W. Gilley, “The Poisoning Effect of Copper Lattices in Aqueous Solutions of Enriched Uranyl Oxyfluoride,” in “Neutron Physics Division Annual Progress Report for Period Ending September 1, 1959,” Oak Ridge National Laboratory report ORNL-2842 (November 1959), pp. 73-76
128. L. W. Gilley, D. F. Cronin, and V. G. Harness, “Boron Poisoning in Critical Slabs,” in “Physics Division Semiannual Progress Report for Period Ending March 10, 1954,” Oak Ridge National Laboratory report ORNL-1715 (July 1954), pp. 12,13.
129. L. W. Gilley and Dixon Callihan, “Nuclear Safety Tests on a Proposed Ball Mill,” Oak Ridge National Laboratory report ORNL-CF-54-9-89 (September 1954).
130. J. K. Fox and L. W. Gilley, “Critical Parameters for 20-in.-diam Stainless Steel Cylinders Containing Aqueous Solutions of U235 Poisoned with Pyrex Glass,” in “Neutron Physics Division Annual Progress Report for Period Ending September 1, 1959,” Oak Ridge National Laboratory report ORNL-2842 (November 1959), pp. 78-81.
131. R. C. Lloyd, “Summary Listing of Subcritical Measurements of Heterogeneous Water-Uranium Lattices Made at Hanford,” Hanford Atomic Products Operation report HW-65552 (June 1960).
132. H. Kouts and R. Sher, “Experimental Studies of Slightly Enriched Uranium, Water-Moderated Lattices,” Brookhaven National Laboratory report BNL-486 (September 1957).
133. W. H. Arnold, Jr., “Critical Masses and Lattice Parameters Of H2O-UO2 Critical Experiments. A Comparison of Theory and Experiment,” Westinghouse Atomic Power Department report YAEC-152 (November 1959).
134. R. C. Lloyd, B. M. Durst, and E. D. Clayton, “Effect of Soluble Neutron Absorbers on the Criticality of Low-Uranium-235-Enriched UO2 Lattices,” Nucl. Sci. Eng. 71, 164-169 (1979).
135. G. E. Hansen and D. P. Wood, “Precision Critical Mass Determinations for Oralloy and Plutonium in Spherical Tuballoy Tampers,” Los Alamos Scientific Laboratory report LA-1356 (Del.) (February 1952).
136. G. E. Hansen, H. C. Paxton, and D. P. Wood, “Critical Masses of Oralloy in Thin Reflectors,” Los Alamos Scientific Laboratory report LA-2203 (July 1958).
137. D. C. Coonfield, Grover Tuck, H. E. Clark, and B. B. Ernst, “Critical Mass Irregularity of Steel-Moderated Enriched Uranium Metal Assemblies with Composite Steel-Oil Reflectors,” Nucl. Sci. Eng. 39, 320-328 (1970).
138. J. R. Dominey, R. C. Lane, and A. F. Thomas, “Critical Mass Measurements with Thin Discs of 45.5% Enriched Uranium,” United Kingdom Atomic Energy Authority report AWRE NR/A-1/62, Aldermaston (January 1962).
139. J. J. McEnhill and J. W. Weale, “Integral Experiments on Fast Systems of Plutonium, Uranium, and Thorium,” in Proc. of Conf. on Physics of Fast and Intermediate Reactors, Vienna (International Atomic Energy Agency, Vienna, 1962), Vol. I, pp. 253-262.
140. E. A. Plassman and D. P. Wood, “Critical Reflector Thicknesses for Spherical U233 and Pu239 Systems,” Nucl. Sci. Eng. 8, 615-620 (1960).
141. G. E. Hansen and H. C. Paxton, “Reevaluated Critical Specifications of Some Los Alamos Fast-Neutron Systems,” Los Alamos Scientific Laboratory report LA-4208 (September 1969).
142. H. R. Ralston, “Critical Parameters of Spherical Systems of Alpha-Phase Plutonium Reflected by Beryllium,” University of California Radiation Laboratory report UCRL- 5349 (September 1958).
143. R. E. Rothe and I. Oh, “Benchmark Critical Experiments on High-Enriched Uranyl Nitrate Solution Systems,” Nucl. Technol. 41, 207-225 (1978).
144. E. B. Johnson and C. E. Newlon, “The Effect of Steel-Water Reflectors on the Criticality of Low-Enriched Uranyl Fluoride Solution,” Trans. Am. Nucl. Soc. 11, 383,384 (1968).
145. L. B. Engle, G. E. Hansen, and H. C. Paxton, “Reactivity Contributions of Various Materials in Topsy, Godiva, and Jezebel,” Nucl. Sci. Eng. 8, 543-569 (1960).
146. D. P. Wood, C. C. Byers, and L. C. Osborn, “Critical Masses of Cylinders of Plutonium Diluted with Other Metals,” Nucl. Sci. Eng. 8, 578-587 (1960).
147. A. J. Kirschbaum, “Studies of Enriched Uranium Graphite Reactor Systems,” University of California Radiation Laboratory report UCRL-4983-T (November 1957).
148. J. E. Schwager, F. A. Kloverstrom, and W. S. Gilbert, “Critical Measurements on Intermediate-Energy Graphite-U235 Systems,” University of California Radiation Laboratory report UCRL-5006 (November 1957).
149. H. L. Reynolds, “Critical Measurements and Calculations for Enriched-Uranium Graphite-Moderated Systems,” in Proceedings of the Second International Conference on the Peaceful Uses of Atomic Energy, Geneva, 1958 (United Nations, New York, 1958), Vol. 12, pp. 632-642.
150. F. A. Kloverstrom, R. M. R. Deck, and A. J. Reyenga, “Critical Measurements on Near-Homogeneous BeO-Moderated, Enriched-Uranium Fueled Systems,” Nucl. Sci. Eng. 8, 221-225 (1960).
151. E. L. Zimmerman, “Two Beryllium-Moderated Critical Assemblies,” Oak Ridge National Laboratory report ORNL-2201 (October 1958).
152. R. N. Olcott, “Homogeneous Heavy Water Moderated Critical Assemblies, Part 1, Experimental,” Nucl. Sci. Eng. 1, 327-341 (1956).
153. A. Goodwin, Jr., and C. L. Schuske, “Plutonium Graphite Assemblies,” Dow Chemical Company Rocky Flats Plant report RFP-158 (August 1959).
154. A. Goodwin, Jr., and C. L. Schuske, “Plutonium Graphite Assemblies,” Dow Chemical Co., Rocky Flats Plant report RFP-123 (September 1958).
155. J. K. Fox and L. W. Gilley, “Critical Parameters for Poisoned Annular Cylinders Containing Aqueous Solutions of U235,” in “Neutron Physics Division Annual Progress Report for Period Ending September 1, 1958,” Oak Ridge National Laboratory report ORNL-2609 (October 1958), pp. 31-33.
156. J. E. Tanner and H. M. Forehand, “Critical Experiments for Large Scale Enriched Uranium Solution Handling,” in Proc. of Topical Meeting on Criticality Safety in the Storage of Fissile Material, September 8-11, 1985, Jackson, Wyoming (American Nuclear Society report ISBN:89448-119-3, 1985), pp. 65-79.
157. C. Clouet d’Orval, E. Deilgat, M. Houelle, and P. Lécorché, “Experimental Research in France on Criticality Problems,” (in French) in Proceedings of the Symposium Criticality Control of Fissile Materials, 5tockholm, 1-5 November 1965 (International Atomic Energy Agency, Vienna, 1966), pp. 193-213.
158. J. T. Mihalczo, “Critical Experiments and Calculations with Annular Cylinders of U(93.2) Metal,” in “Neutron Physics Division Annual Progress Report for Period Ending August 1, 1963,” Oak Ridge National Laboratory report ORNL-3499 (October 1963), Vol. 1, pp. 62-63.
159. E. B. Johnson, “The Nuclear Criticality of Intersecting Cylinders of Aqueous Uranyl Fluoride Solutions,” Union Carbide Corp., Y-12 Plant report Y-DR-129 (October 1974).
160. Bruce B. Ernst and C. L. Schuske, “Empirical Method for Calculating Pipe Intersections Containing Fissile Solutions,” Dow Chemical Co., Rocky Flats Plant report RFP-1197 (September 1968).
161. C. E. Newlon, “The Uses of Criticality Codes in Nuclear Safety Considerations of the Oak Ridge Gaseous Diffusion Plant,” Oak Ridge Gaseous Diffusion Plant report AECU-4173 (April 1959).
162. C. L. Schuske and J. W. Morfitt, “An Empirical Study of Some Critical Mass Data,” Carbide and Carbon Chemicals Corp., Y-12 Plant report Y-533 (December 1949).
163. Deanne Dickinson and C. L. Schuske, “An Empirical Model for Safe Pipe Intersections Containing Fissile Solution,” Nucl. Technol. 10, 179-187 (1971).
164. N. F. Cross, G. E. Whitesides, and R. J. Hinton, “Monte Carlo Analysis of Experimentally Critical Pipe Intersections,” Trans. Am. Nucl. Soc. 17, 268 (1973).
165. Deanne Dickinson, “Nominally Reflected Pipe Intersections Containing Fissile Solution,” Nucl. Technol. 26, 265-277 (1975)
166. “Nuclear Criticality Safety Criteria for Steel-Pipe Intersections Containing Aqueous Solutions of Fissile Materials,” ANSI/ANS-8.9-1987 (American National Standards Institute, Inc., New York, 1987).
167. J. T. Thomas, “Reflectors, Infinite Cylinders, and Nuclear Criticality,” Nucl. Sci. Eng. 67, 279-295 (1978).
168. Dixon Callihan, D. F. Cronin, J. K. Fox, R. L. Macklin, and J. W. Morfitt, “Critical Mass Studies, Part IV,” Carbide and Carbon Chemicals Corp., K-25 Plant report K-406 (November 1949).
169. L. W. Gilley, D. F. Cronin, J. K. Fox, and J. T. Thomas, “Critical Arrays of Neutron-Interacting Units,” in “Neutron Physics Division Annual Progress Report for Period Ending September 1, 1961,” Oak Ridge National Laboratory report ORNL-3193 (October 1961), pp. 159-167.
170. J. K. Fox and L. W. Gilley, “Critical Parameters of Unreflected Arrays of Interacting Cylinders Containing Aqueous Solutions of U235,” in “Neutron Physics Division Annual Progress Report for Period Ending September 1, 1959,” Oak Ridge National Laboratory report ORNL-2842 (November 1959), pp. 82-84.
171. J. K. Fox and L. W. Gilley, “Critical Parameters of Aqueous Solutions of U235,” in “Neutron Physics Division Annual Progress Report for Period Ending September 1, 1957,” Oak Ridge National Laboratory report ORNL-2389 (October 1957), pp. 71-83.
172. A. V. Kamaev, B. G. Dubovskii, V. V. Vavilov, G. A. Popov, Yu. D. Palamarchuk, and S. P. Ivanov, “Experimental Investigation of Effects of Interaction of Two Subcritical Reactors,” translated from a publication of the State Committee of the Council of Ministers of the USSR on the Utilization of Atomic Energy, Moscow, 1960, U. S. Atomic Energy Commission report AEC-tr-4708 (U. S. Department of Energy, Technical Information Center, Oak Ridge, Tennessee).
173. B. G. Dubovskii, A. V. Kamaev, G. M. Vladykov, F. M. Kuznetsov, V. Z. Nozik, Yu. D. Palamarchuk, G. A. Popov, and V. V. Vavilov, “Interaction of Subcritical Reactors,” J. Nucl. Energy, Parts A/B 19, 271-277 (1965).
174. J. K. Fox and L. W. Gilley, “Some Studies of Water, Styrofoam, and Plexiglas Reflectors,” in “Neutron Physics Division Annual Progress Report for Period Ending September 1, 1958,” Oak Ridge National Laboratory report ORNL-2609 (October 1958), pp. 38-40.
175. Grover Tuck and H. E. Clark, “Critical Parameters of a Uranium Solution Slab-Cylinder System,” Nucl. Sci. Eng. 40, 407-413 (1970).
176. E. B. Johnson, “Critical Dimensions of Arrays of Aqueous Uranyl Fluoride Solution Containing Uranium Enriched to 5% in 235U,” in “Neutron Physics Division Annual Progress Report for Period Ending August 1, 1965,” Oak Ridge National Laboratory report ORNL-3858 (November 1965), pp. 15,16.
177. J. T. Thomas, “Experimental and Calculated System Criticality,” in Proceedings of the Symposium Criticality Control of Fissile Materials, Stockholm, 1-5 November 1965 (International Atomic Energy Agency, Vienna, 1966), pp. 149-175.
178. C. L. Schuske, “Two Experimental Subcritical Arrays of Pu(NO3)4 Solution,” Dow Chemical Co., Rocky Flats Plant report RFP-325 (July 1963).
179. J. C. Bouly, R. Caizergues, E. Deilgat, M. Houelle, and L. Maubert, “Neutron Interaction in Air Between Cylindrical Containers Holding Either Uranium or Plutonium Solutions,” (in French) Commissariat a l’Energie Atomique report CEA-R-3946 (March 1970).
180. B. M. Durst, E. D. Clayton, and J. H. Smith, “Critical Experiments with Arrays of Three-Liter Bottles Filled with Pu(2.8)(NO3)4,” Trans. Am. Nucl. Soc. 41, 356-358 (1982).
181. J. T. Thomas, “Criticality of 233U Aqueous Nitrate Solution in Reflected and Unreflected Arrays,” Trans. Am. Nucl. Soc. 10, 538,539 (1967).
182. R. C. Lloyd, E. D. Clayton, and J. H. Chalmers, “Criticality of Arrays of 233U Solution,” Nucl. Appl. 4, 136-141 (1968).
183. J. T. Thomas, “Critical Three-Dimensional Arrays of Neutron-Interacting Units,” Oak Ridge National Laboratory report ORNL-TM-719 (October 1963).
184. S. R. Bierman, B. M. Durst, and E. D. Clayton, “Criticality Experiments with Subcritical Clusters of Low Enriched UO2 Rods in Water with Uranium or Lead Reflecting Walls,” Nucl. Technol. 47, 51-58 (1980).
185. S. R. Bierman and E. D. Clayton, “Criticality Experiments with Subcritical Clusters of 2.35 and 4.31 wt% 235U-Enriched Rods in Water with Steel Reflecting Walls,” Nucl. Technol. 54, 131-144 (1981).
186. J. T. Mihalczo, “Prompt-Neutron Decay in a Two Component Enriched-Uranium-Metal Critical Assembly,” Trans. Am. Nucl. Soc. 6, 60,61 (1963).
187. J. T. Thomas, “Critical Experiments with UF6 Cylinder Model 8A Containers,” Union Carbide Corp., Y-12 Plant report Y-DR-128 (September 1974).
188. T. G. McCreless, D. R. Smith, G. A. Jarvis, and Dick Duffy, “Neutronic Isolation Characteristics of Concrete, Lead, Wood, Polyethylene, and Beryllium,” Trans. Am. Nucl. Soc. 8, 441 (1965).
189. J. D. White and C. R. Richey, “Neutron Interaction Between Multiplying Media Separated by Various Materials,” Trans. Am. Nucl. Soc.8, 441,442 (1965).
190. J. T. Mihalczo and J. J. Lynn, “Multiplication Measurements with Highly Enriched Uranium Metal Slabs,” Oak Ridge National Laboratory report ORNL-CF-59-7-87 (July 1959).
191. J. T. Thomas, “Critical Three-Dimensional Arrays of U(93.2)-Metal Cylinders,” Nucl. Sci. Eng. 52, 350-359 (1973).
192. E. C. Crume and J. T. Thomas, “Critical and Near-Critical Graphite-Moderated Arrays of U(93.2) Cylinders,” Trans. Am. Nucl. Soc. 12, 336,337 (1969).
193. C. L. Schuske, C. L. Bell, G. H. Bidinger, and D. F. Smith, “Industrial Criticality Measurements on Enriched Uranium and Plutonium. Part II,” Dow Chemical Co., Rocky Flats Plant report RFP-248 (January 1962).
194. C. L. Schuske, A. Goodwin, Jr., G. H. Bidinger, and D. F. Smith, “Interaction of Two Metal Slabs of Plutonium in Plexiglas,” Dow Chemical Co., Rocky Flats Plant report RFP-174 (December 1959).
195. O. C. Kolar, H. F. Finn, and N. L. Pruvost, “Livermore Plutonium Program: Experiments and Calculations,” Nucl. Technol. 29, 57-72 (1976).
