71. Dietrich, J. R., and D. C. Layman. Transient and Steady State Characteristics <strong>of</strong> a Boiling Reactor. The Borax Experiments, 1953. Argonne National Laboratory, Argonne, IL, AECD-3840, (1954). 72. Thompson, T. J., and J. G. Beckerley, Eds. The Technology <strong>of</strong> Nuclear Reactor Safety, vol. 1 (The M.I.T. Press, Cambridge, MA, 1964). 73. Lushbaugh, C. C. “Reflections on Some Recent Progress in Human Radiobiology.” In Advances in Radiation Biology, vol. 3, L. G. Augenstein, R. Mason, and M. Zelle, Eds. (Academic Press Inc., pp 277–314., (1969). 74. Tardiff, A. N. “Some Aspects <strong>of</strong> the WTR and SL-1 <strong>Accidents</strong>.” In Proc. Symp. Reactor Safety and Hazards Evaluation Techniques. vol. 1, International Atomic Energy Agency, Vienna, pp. 43–88, (1962). 75. Nyer, W. E., G. O. Bright, and R. J. McWhorter. “Reactor Excursion Behavior.” In Proc. UN Intern. Conf. Peaceful Uses At. Energy, 3rd, Geneva, 1964, vol. 13, United Nations, Geneva, pp. 13–25, (1965). 76. Miller, R. W., A. Sola, and R. K. McCardell, “Report <strong>of</strong> the SPERT-1 Destructive Test Program on an Aluminum, Plate-type, Water-Moderated Reactor,” Phillips Petroleum Company, IDO-16883, (June 1964). 77. Parfanovich, D. M. Summary <strong>of</strong> Two <strong>Criticality</strong> <strong>Accidents</strong> at the Russian Research Center “Kurchatov Institute.” INEEL/EXT-98-00409, Idaho National Engineering and Environmental Laboratory, J. Blair Briggs, ed., (August 1998). 78. “Water-Moderated Hexagonally Pitched Lattices <strong>of</strong> U(9O%)O2 + Cu Fuel Rods with GD or SM Rods.” HEU-COMP-THERM-004, International Handbook <strong>of</strong> Evaluated <strong>Criticality</strong> Safety Benchmark Experiments, NEA/N S C/DOC(95)03/II, 1996 Version or Later. 79. US NRC Information Notice No. 83-66, Supplement 1: Fatality at Argentine Critical Facility, (May 25, 1984). 80. Frisch, O. R. Controlled Production <strong>of</strong> an Explosive Nuclear Chain Reaction. Los Alamos Scientific Laboratory, Los Alamos, NM, LA-397, (1945). 81. De H<strong>of</strong>fman, F., B. T. Feld, and P. R. Stein. “Delayed Neutrons from 235U After Short Irradiation.” Phys. Rev., 74, (10) 1330–1337, (1948). 114 82. Brittan, R. O. “Analysis <strong>of</strong> the EBR-1 Core Meltdown.” In Proc. UN Intern. Conf. Peaceful Uses At. Energy, 2nd Geneva, 1958, vol. 12, United Nations, Geneva, pp. 267–272, (1958). 83. Kittel, J. H., M. Novick, and R. F. Buchanan. The EBR-1 Meltdown—Physical and Metallurgical Changes in the Core. Argonne National Laboratory, Argonne, IL, ANL-5731, (1957). 84. Summary Report <strong>of</strong> HTRE No. 3 Nuclear Excursion. General Electric Co., Aircraft Nuclear Propulsion Dept., Cincinnati, OH, APEX-509, (1959). 85 Remley, M. E., J. W. Flora, D. L. Hetrick, D. R. Muller, E. L. Gardner, R. E. Wimmer, R. K. Stitt, and D. P. Gamble. “Experimental Studies on the Kinetic Behavior <strong>of</strong> Water Boiler Type Reactors.” In Proc. UN Intern. Conf. Peaceful Uses At. Energy, 2nd, Geneva 1958, vol. 11, United Nations, Geneva, pp. 447–456 (1958). 86. Stitt, R. K. “A Summary <strong>of</strong> Experimental Results <strong>of</strong> the Spherical Core Investigations in the Kewb Program.” Nucl. Sci. Eng., 2 (1), Suppl., 212–213, (1959). 87. Hetrick, D. L., J. W. Flora, E.L. Garner, et.al. “Preliminary Results on the Kinetic Behavior <strong>of</strong> Water Boiler Reactors.” Atomics International, North American Aviation, NAA-SR-1896, (April 15, 1987). 88. Malenfant, R. E., H. M. Forehand, and J. J. Koelling. “SHEBA: A Solution Critical Assembly.” Trans. Amer. Nucl. Sec. 35 p. 279, (1980). 89. Forbes, S. G., F. L. Bentzen, P. French, J. E. Grund, I. C. Haire, W. E. Nyer, and R. F. Walker. Analysis <strong>of</strong> Self-Shutdown Behavior in the SPERT-1 Reactor. Phillips Petroleum Company, Atomic Energy Div., Idaho Falls, Idaho, IDO-16528, (1959). This reference has been carried over from a previous edition <strong>of</strong> the document. At the time <strong>of</strong> printing it was not possible to locate a copy <strong>of</strong> the document. 90. Nyer, W. E., and S. G. Forbes. “SPERT-1 Reactor Safety Studies.” In Proc. UN Intern. Conf. Peaceful Uses At. Energy, 2nd, Geneva, 1958, vol. 11, United Nations, Geneva, pp. 470–480, (1958). 91. Schroeder, F., S. G. Forbes, W. E. Nyer, F. L. Bentzen, and G. O. Bright. “Experimental Study <strong>of</strong> Transient Behavior in a Subcooled, Water-Moderated Reactor.” Nucl. Sci. Eng. 2, 96–115, (1957).
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LA-13638 Approved for public releas
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A Review of Criticality Accidents 2
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PREFACE This document is the second
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Tom Jones was invaluable in generat
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C. OBSERVATIONS AND LESSONS LEARNED
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FIGURES 1. Chronology of process cr
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51. MSKS and assembly involved in t
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A REVIEW OF CRITICALITY ACCIDENTS A
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3 Black Sea Baltic Sea Obninsk Norw
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North Atlantic Ocean Irish Sea Wind
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1. Mayak Production Association, 15
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time of the accident. However, the
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determined by a radiation control p
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consequences of this accident, the
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Figure 10. Drum in which the 1958 Y
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The entire plutonium process area h
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7. Mayak Production Association, 5
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During the next shift, radiation sa
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9. Siberian Chemical Combine, 14 Ju
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The accident investigation determin
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10. Hanford Works, 7 April 1962 18,
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heater and stirrer were turned off
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vessel 64-A was added. The dissolut
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additional reflection afforded by t
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15. Electrostal Machine Building Pl
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16. Mayak Production Association, 1
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ased on a radiation survey, that th
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0.5 m 0.5 m 0.5 m 0.5 m 3.0 m 1.4 m
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The investigation identified severa
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19. Idaho Chemical Processing Plant
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20. Siberian Chemical Combine, 13 D
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To Glovebox 6 7 8 6 From Glovebox 6
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on a 0.4 m square pitch grid. The b
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competing reactivity effects proved
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Figure 35. The precipitation vessel
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B. PHYSICAL AND NEUTRONIC CHARACTER
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Material Fissile Mass: Fissile mass
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235 U Spherical Critical Mass (kg)
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