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The grave weaknesses apparent in engineering knowledge of emergency core-cooling systems and the strong implications that these systems would fail to terminate safely a loss-of-coolant accident make it clear that in the event of a major reactor accident the United States might easily suffer a peacetime catastrophe, the scale of which might well exceed anything the nation has ever known.
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References and Notes
Science, May 28, 1971, p. 191.
Lawson, C. G. Emergency Core-Cooling Systems for Light-Water-Coled Power Reactors, Oak Ridge National Laboratories, ORNL-NSIC-24, Oak Ridge, Term., 1968, p. 52.
Report of the Task Force Established by the USAEC to Study Fuel Cooling Systems of Nuclear Power Plants, Emergency Core Cooling, 1967, p. 145.
Battelle Memorial Institute Reports, BMI-1825 and BMI-1910.
Waddell, R. D. “Measurement of Light Water Reactor Coolant Channel Reduction Arising from Cladding Defermation During a Loss-of-Coolant Accident,” Nuclear Technology 11(4): 491, (August 1971).
The report on these tests: Lorenz, R., D. Hobson, and G. Parker, Final Report on the First Fuel Rod Failure Transient Test of A Zircaloy-Clad Fuel Rod Cluster in TREAT, Oak Ridge National Laboratory, (ORNL-4635). Oak Ridge, Term., Mar. 1971.
ORNL TM 3263.
The results are recent and are reported in an Idaho Nuclear Corporation document: M. J. Graber, W. E. Zelensky, and R. E. Schmunk, A Metallurgical Evaluation of Simulated BWR Emergency Core-Cooling Tests (IN-1453), Feb. 1971.
GEAP-13197.
Presentation to AEC Atomic Safety and Licensing Board, Idaho Falls, Idaho, July 1, 1971.
For detailed documentation of the extensive gaps in our experimentally derived understanding of reactor accident phenomena and of the performance capabilities of emergency systems, refer to: Lawson, C. G. Emergency Core-Cooling Systems for Light-Water Cooled Reactors, ORNL-NSIC-24 Oak Ridge National Laboratory, Oak Ridge, Tennessee, 1968. USAEC, Water-Reactor Safety Program Plan, WASH-1146, Feb. 1970. Committee on Reactor Safety Technology (CREST), European Nuclear Energy Agency, Water-Cooled Reactor Safety, OECD, Paris, May 1970, Forbes, Ian A., Daniel F. Ford, Henry W. Kendall, and James J. MacKenzie, Nuclear Reactor Safety: An Evaluation of New Evidence, The Union of Concerned Scientists, Cambridge, Mass., July 1971, reprinted in Nuclear News, Sept. 1971.
AEC News Release, May 27, 1971.
Science, May 28, 1971, p. 919.
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Kendall, H.W. (2000). Cooling Water. In: Kendall, H.W. (eds) A Distant Light. Masters of Modern Physics, vol 0. Springer, New York, NY. https://doi.org/10.1007/978-1-4419-8507-1_5
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