Nuclear Reactor Safety: Hearings Before the Joint Committee on Atomic Energy, Congress of the United States, Ninety-third Congress, First Session ...U.S. Government Printing Office, 1974 - Nuclear reactors |
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Page 556
... limits of present knowledge , an estimate of public risks from potential power reactor accidents . The public hearings on January 22-24 , 1974 on nuclear reactor safety are scheduled to be held in the Joint Committee's public hearing ...
... limits of present knowledge , an estimate of public risks from potential power reactor accidents . The public hearings on January 22-24 , 1974 on nuclear reactor safety are scheduled to be held in the Joint Committee's public hearing ...
Page 577
... limits on design parameters ( in terms of quantities such as time and temperature ) , which , if not exceeded , would provide assurance that the intended function of cooling the core will be accomplished by the specific system provided ...
... limits on design parameters ( in terms of quantities such as time and temperature ) , which , if not exceeded , would provide assurance that the intended function of cooling the core will be accomplished by the specific system provided ...
Page 587
... limits of both the proposed technical specifications or license amendments submitted under the above procedure , and all technical specifications 5. Further restrictions on reactor operation will be imposed by or license conditions ...
... limits of both the proposed technical specifications or license amendments submitted under the above procedure , and all technical specifications 5. Further restrictions on reactor operation will be imposed by or license conditions ...
Page 592
... limit the rate of reflooding the core , reducing it from an intended 6 to 11 inches per second to from 1.0 to 2.5 inches per second , depending on the reactor design . The rule we announce considers all the provides an acceptable ...
... limit the rate of reflooding the core , reducing it from an intended 6 to 11 inches per second to from 1.0 to 2.5 inches per second , depending on the reactor design . The rule we announce considers all the provides an acceptable ...
Page 593
... limits we have set . The occurrence of reflooding within three minutes after a postulated break of the recirculation line would ... limit the power and the power operator in relation to limiting the design basis accident within the given 593.
... limits we have set . The occurrence of reflooding within three minutes after a postulated break of the recirculation line would ... limit the power and the power operator in relation to limiting the design basis accident within the given 593.
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Common terms and phrases
accident AEC's Appendix Atomic Energy Commission blowdown Boiling Water Reactor calculated Concluding Statement control rod control rod drive coolant core cooling systems correlation criteria Director of Regulation Dixy Lee Ray draft ECCS effects Electric emergency core cooling Engineering environmental Equipment Operating Failure/malfunction Equipment Operating Secondary Equipment Startup evaluation models facilities feedwater fission products FLECHT flow forced outages fossil fuel rods hearings heat transfer industry inspection issued Joint Committee leak licensing LOCA loss-of-coolant accident METERS nuclear plants nuclear power plants nuclear reactor Operating Secondary System Operator error oxidation phase physical protection plant availability plutonium potential power reactors pressure Pressurized Water Reactors procedures pump radioactive reactor safety Reactor scram reflood refueling regulatory guides Regulatory Staff release requirements result risk rupture sabotage scheduled outages scram special nuclear material standards uranium valve Water Reactors Westinghouse Yankee Rowe zircaloy
Popular passages
Page 844 - ... (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 764 - ... 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 688 - 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 697 - 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 701 - 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 921 - ... 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...