58. P. D. O'Brien, "Fast Burst Reactor Operational Incidents," in Proceedings of the National Topical Meeting on Fast Burst Reactors, Albuquerque, NM, (U. S. Atomic Energy Commission), pp. 373–384 (January 1969).

59. V. A. Teryokhin, V. D. Perezhogin, and Yu. A. Sokolov, "Criticality Measurements at VNIITF — Review," in Proceedings of the Fifth International Conference on Nuclear Criticality Safety, Albuquerque, NM, Vol. 1, pp. 4.44—4.47 (September 1995).

60. N. P. Voloshin, I. S. Pogrebov, and V. A. Teryokhin, "RFNC–VNIITF Physical Experimental

Division and a Short Historical Sketch of Critical Mass Measurements," in Proceedings of the Fifth International Conference on Nuclear Criticality Safety, Albuquerque, NM, Vol. 1, pp. P.31—P.36 (September 1995).

61. A. H. Kazi, H. G. Dubyoski, and R. W. Dickinson, "Preoperational Test Experience with the Army Pulse Radiation Facility Reactor," in Proceedings of the National Topical Meeting on Fast Burst Reactors, Albuquerque, NM (U. S. Atomic Energy Commission), pp. 353–371 (January 1969).

62. Н. П. Волошин, "По материалам заключения комиссии о причинах ядерной аварии в РФЯЦ-ВНИИЭФ в г. Сарове", Атомпресса, № 26 (262), июль 1997 г.

63. В. Т. Пунин, И. Г. Смирнов, С. А. Зыков, "Авария на стенде критических сборок в РФЯЦ-ВНИИЭФ", Атомная энергия, том 83, вып. 2, с. 154–156, август 1997 г.

64. Г. Ф. Ходалев и др., "Доза облучения экспериментатора при аварии на критической сборке в РФЯЦ-ВНИИЭФ", Атомная энергия, том 85, вып. 2, с. 153–158, август 1998 г.

65. H. F. McFarland, Controlled Nuclear Chain Reaction: The First 50 Years (American Nuclear Society, La Grange Park, IL), pp. 52–54 (1992).

66. D. G. Hurst and A. G. Ward, "Canadian Research Reactors," in Progress in Nuclear Energy, Series II, REACTORS (Pergamon Press, London), Vol. 1, pp. 1—48 (1956).

67. R. O. Brittan, R. J. Hasterlik, L. D. Marinelli, and F. W. Thalgott, "Technical Review of ZPR-1 Accidental Transient — The Power Excursion, Exposures, and Clinical Data," Argonne National Laboratory report ANL-4971 (January 1953).

68. W. B. Lewis, "The Accident to the NRX Reactor on December 12, 1952," Atomic Energy of Canada Ltd. report DR-32 (July 1953).

69. W. J. Henderson, A. C. Johnson, and P. R. Tunnicliffe, "An Investigation of Some of the Circumstances Pertinent to the Accident to the NRX Reactor of December 12, 1952," Atomic Energy of Canada Ltd. report NEI-26 (March 1953).

70. J. R. Dietrich, et al., "Experimental Investigation of the Self-limitation of Power During Reactivity Transients in a Subcooled, Water-moderated Reactor, Borax-I Experiments, 1954," Argonne National Laboratory report ANL-5323 (1954).

71. "Reactors, Operational Power Reactors," Nucleonics 13 (9), 40–45 (September 1955).

72. J. R. Dietrich, "Experimental Determinations of the Self-regulation and Safety of Operating Water-moderated Reactors," in Proceedings of the United Nations International Conference on the Peaceful Uses of Atomic Energy, Geneva, Vol. 13, pp. 88—101 (August 1955).

73. J. R. Dietrich and D. C. Layman, "Transient and Steady State Characteristics of a Boiling Reactor, The Borax Experiments, 1953," Argonne National Laboratory report AECD-3840 (February 1954).

74. T. J. Thompson, "Chapter 11 — Accidents and Destructive Tests," The Technology ofNuclear Reactor Safety (The M. I. T. Press, Cambridge, MA), Vol. 1, pp. 609–610, 699 (1964).

75. "Yugoslavian Criticality Accident, October 15, 1958," Nucleonics, 17 (4), 106, 154–156 (April 1959).

76. C. C. Lushbaugh, "Reflections on Some Recent Progress in Human Radiobiology," in Advances in Radiation Biology (Academic Press Inc., New York), Vol. 3, pp. 292–293 (1969).

77. A. N. Tardiff, "Some Aspects of the WTR and SL-1 Accidents," in Proceedings of the IAEA Symposium on Reactor Safety and Hazards Evaluation Techniques, Vienna, Vol. 1, pp. 43–88 (May 1962).

78. W. E. Nyer, G. O. Bright, and R. J. McWhorter, "Reactor Excursion Behavior," in Proceedings of the Third United Nations International Conference on the Peaceful Uses of Atomic Energy, Geneva, Vol. 13, pp. 13–25 (August 1964).

79. R. W. Miller, A. Sola, and R. K. McCardell, "Report of the SPERT I Destructive Test Program on an Aluminum, Plate-type, Water-moderated Reactor," Phillips Petroleum Company report IDO-16883 (June 1964).

80. D. M. Parfanovich, "Summary of Two Criticality Accidents at the Russian Research Center Kurchatov Institute," Idaho National Engineering and Environmental Laboratory report INEEL/EXT-98-00409 (August 1998).

81. A. Yu. Gagarinski and V. D. Pavlov, "Water-moderated Hexagonally Pitched Lattices of U(90 %)O2 + Cu Fuel Rods with GD or SM Rods," HEU-COMP-THERM-004 in International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC(95)-03, Vol. II (September 2002).