A Review of Criticality Accidents A Review of Criticality Accidents
A Review of Criticality Accidents A Review of Criticality Accidents
A Review of Criticality Accidents A Review of Criticality Accidents
Create successful ePaper yourself
Turn your PDF publications into a flip-book with our unique Google optimized e-Paper software.
71. Dietrich, J. R., and D. C. Layman. Transient and<br />
Steady State Characteristics <strong>of</strong> a Boiling Reactor.<br />
The Borax Experiments, 1953. Argonne National<br />
Laboratory, Argonne, IL, AECD-3840, (1954).<br />
72. Thompson, T. J., and J. G. Beckerley, Eds. The<br />
Technology <strong>of</strong> Nuclear Reactor Safety, vol. 1<br />
(The M.I.T. Press, Cambridge, MA, 1964).<br />
73. Lushbaugh, C. C. “Reflections on Some Recent<br />
Progress in Human Radiobiology.” In Advances in<br />
Radiation Biology, vol. 3, L. G. Augenstein,<br />
R. Mason, and M. Zelle, Eds. (Academic Press<br />
Inc., pp 277–314., (1969).<br />
74. Tardiff, A. N. “Some Aspects <strong>of</strong> the WTR and<br />
SL-1 <strong>Accidents</strong>.” In Proc. Symp. Reactor Safety<br />
and Hazards Evaluation Techniques. vol. 1,<br />
International Atomic Energy Agency, Vienna,<br />
pp. 43–88, (1962).<br />
75. Nyer, W. E., G. O. Bright, and R. J. McWhorter.<br />
“Reactor Excursion Behavior.” In Proc. UN<br />
Intern. Conf. Peaceful Uses At. Energy, 3rd,<br />
Geneva, 1964, vol. 13, United Nations, Geneva,<br />
pp. 13–25, (1965).<br />
76. Miller, R. W., A. Sola, and R. K. McCardell,<br />
“Report <strong>of</strong> the SPERT-1 Destructive Test Program<br />
on an Aluminum, Plate-type, Water-Moderated<br />
Reactor,” Phillips Petroleum Company,<br />
IDO-16883, (June 1964).<br />
77. Parfanovich, D. M. Summary <strong>of</strong> Two <strong>Criticality</strong><br />
<strong>Accidents</strong> at the Russian Research Center<br />
“Kurchatov Institute.” INEEL/EXT-98-00409,<br />
Idaho National Engineering and Environmental<br />
Laboratory, J. Blair Briggs, ed., (August 1998).<br />
78. “Water-Moderated Hexagonally Pitched Lattices<br />
<strong>of</strong> U(9O%)O2 + Cu Fuel Rods with GD or SM<br />
Rods.” HEU-COMP-THERM-004, International<br />
Handbook <strong>of</strong> Evaluated <strong>Criticality</strong> Safety Benchmark<br />
Experiments, NEA/N S C/DOC(95)03/II,<br />
1996 Version or Later.<br />
79. US NRC Information Notice No. 83-66,<br />
Supplement 1: Fatality at Argentine Critical<br />
Facility, (May 25, 1984).<br />
80. Frisch, O. R. Controlled Production <strong>of</strong> an<br />
Explosive Nuclear Chain Reaction. Los Alamos<br />
Scientific Laboratory, Los Alamos, NM, LA-397,<br />
(1945).<br />
81. De H<strong>of</strong>fman, F., B. T. Feld, and P. R. Stein.<br />
“Delayed Neutrons from 235U After Short<br />
Irradiation.” Phys. Rev., 74, (10) 1330–1337,<br />
(1948).<br />
114<br />
82. Brittan, R. O. “Analysis <strong>of</strong> the EBR-1 Core<br />
Meltdown.” In Proc. UN Intern. Conf. Peaceful<br />
Uses At. Energy, 2nd Geneva, 1958, vol. 12,<br />
United Nations, Geneva, pp. 267–272, (1958).<br />
83. Kittel, J. H., M. Novick, and R. F. Buchanan. The<br />
EBR-1 Meltdown—Physical and Metallurgical<br />
Changes in the Core. Argonne National<br />
Laboratory, Argonne, IL, ANL-5731, (1957).<br />
84. Summary Report <strong>of</strong> HTRE No. 3 Nuclear<br />
Excursion. General Electric Co., Aircraft Nuclear<br />
Propulsion Dept., Cincinnati, OH, APEX-509,<br />
(1959).<br />
85 Remley, M. E., J. W. Flora, D. L. Hetrick,<br />
D. R. Muller, E. L. Gardner, R. E. Wimmer,<br />
R. K. Stitt, and D. P. Gamble. “Experimental<br />
Studies on the Kinetic Behavior <strong>of</strong> Water Boiler<br />
Type Reactors.” In Proc. UN Intern. Conf.<br />
Peaceful Uses At. Energy, 2nd, Geneva 1958,<br />
vol. 11, United Nations, Geneva, pp. 447–456<br />
(1958).<br />
86. Stitt, R. K. “A Summary <strong>of</strong> Experimental Results<br />
<strong>of</strong> the Spherical Core Investigations in the Kewb<br />
Program.” Nucl. Sci. Eng., 2 (1), Suppl., 212–213,<br />
(1959).<br />
87. Hetrick, D. L., J. W. Flora, E.L. Garner, et.al.<br />
“Preliminary Results on the Kinetic Behavior <strong>of</strong><br />
Water Boiler Reactors.” Atomics International,<br />
North American Aviation, NAA-SR-1896,<br />
(April 15, 1987).<br />
88. Malenfant, R. E., H. M. Forehand, and<br />
J. J. Koelling. “SHEBA: A Solution Critical Assembly.”<br />
Trans. Amer. Nucl. Sec. 35 p. 279,<br />
(1980).<br />
89. Forbes, S. G., F. L. Bentzen, P. French,<br />
J. E. Grund, I. C. Haire, W. E. Nyer, and<br />
R. F. Walker. Analysis <strong>of</strong> Self-Shutdown Behavior<br />
in the SPERT-1 Reactor. Phillips Petroleum<br />
Company, Atomic Energy Div., Idaho Falls,<br />
Idaho, IDO-16528, (1959). This reference has<br />
been carried over from a previous edition <strong>of</strong> the<br />
document. At the time <strong>of</strong> printing it was not<br />
possible to locate a copy <strong>of</strong> the document.<br />
90. Nyer, W. E., and S. G. Forbes. “SPERT-1 Reactor<br />
Safety Studies.” In Proc. UN Intern. Conf.<br />
Peaceful Uses At. Energy, 2nd, Geneva, 1958,<br />
vol. 11, United Nations, Geneva, pp. 470–480,<br />
(1958).<br />
91. Schroeder, F., S. G. Forbes, W. E. Nyer,<br />
F. L. Bentzen, and G. O. Bright. “Experimental<br />
Study <strong>of</strong> Transient Behavior in a Subcooled,<br />
Water-Moderated Reactor.” Nucl. Sci. Eng. 2,<br />
96–115, (1957).