Nuclear Reactor Safety: Hearings Before the Joint Committee on Atomic Energy, Congress of the United States, Ninety-third Congress, First Session ...

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Page 842 - ... (7) investigatory files compiled for law enforcement purposes except to the extent available by law -to a party other than an agency; (8) contained in or related to examination, operating, or condition reports prepared by, on behalf of, or for the use of an agency responsible for the regulation or supervision of financial institutions; or (9) geological -and geophysical information and data, including maps, concerning wells.
Page 762 - ... the development, use, and control of atomic energy shall be directed so as to make the maximum contribution to the general welfare, subject at all times to the paramount objective of making the maximum contribution to the common defense and security ; and a.
Page 684 - RA Lee, W. J. Oberjohn, RH Wilson, LJ Stanek, "Correlation of Critical Heat Flux in a Bundle Cooled by Pressurized Water," TwoPhase Flow and Heat Transfer in Rod Bundles, ASME, New York, 1969. (3) Hench-Levy. JM Healzer, JE Hench, E. Janssen, S. Levy, "Design Basis for Critical Heat Flux Condition in Boiling Water Reactors," APED-5186, GE Company Private report, July 1966.
Page 695 - quality assurance" comprises all those planned and systematic actions necessary to provide adequate confidence that a structure, system, or component will perform satisfactorily In service.
Page 601 - ... hydrogen generated from the chemical reaction of the cladding with water or steam shall not exceed 0.01 times the hypothetical amount that would be generated if all...
Page 558 - MS in nuclear physics from the University of California, Berkeley. He is a member of the American Nuclear Society, and chairs the AIF Committee on Reactor Licensing and Safety.
Page 681 - Loss of coolant accidents mean those postulated accidents that result from the loss of reactor coolant at a rate in excess of the capability of the reactor coolant makeup system from breaks in the reactor coolant pressure boundary, up to and Including a break equivalent in size to the double-ended rupture of the largest pipe of the reactor coolant system.
Page 699 - The Joint Committee concluded that full, free, and frank discussion in public of the hazards involved in any particular reactor would seem to be the most certain way of assuring that the reactors will indeed be safe and that the public will be fully apprised of this fact.
Page 683 - Decay Energy Release Rates Following Shutdown of Uranium- Fueled Thermal Reactors", Approved by Subcommittee ANS-5, ANS Standards Committee, October 1971). The fraction of the...
Page 919 - ... to estimate the chance of an accident in the year 2000. This is not a valid calculation, however, because it assumes that the reactors to be built during the next 25 years will be the same as those being built today. Experience with other technologies, such as automobiles and aircraft...

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