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 592
... containment atmosphere . In the pressurized water reactors the steam would have to flow through the steam generator and pump to escape through a cold leg break ; the reduction of reflood rate by the relatively high resistance to flow of ...
... containment atmosphere . In the pressurized water reactors the steam would have to flow through the steam generator and pump to escape through a cold leg break ; the reduction of reflood rate by the relatively high resistance to flow of ...
Page 595
... containment atmosphere . In the pressurized water reactors the steam would have to flow through the steam generator and pump to escape through a cold leg break ; the reduction of reflood rate by the relatively high resistance to flow of ...
... containment atmosphere . In the pressurized water reactors the steam would have to flow through the steam generator and pump to escape through a cold leg break ; the reduction of reflood rate by the relatively high resistance to flow of ...
Page 649
... Containment Systems Experiment at Hanford , the LOFT Semiscale vessel at NRTS , and simple pipe blowdowns by Edwards in England . Some comparisons have also been made with the results of other experiments including some by vendors . The ...
... Containment Systems Experiment at Hanford , the LOFT Semiscale vessel at NRTS , and simple pipe blowdowns by Edwards in England . Some comparisons have also been made with the results of other experiments including some by vendors . The ...
Page 652
... containment pressures and to faster core dryout which would cause maximum calculated clad tempera- tures to be higher . It was stated that this tendency would be found especially if the break were near the vessel . Data from experi ...
... containment pressures and to faster core dryout which would cause maximum calculated clad tempera- tures to be higher . It was stated that this tendency would be found especially if the break were near the vessel . Data from experi ...
Page 681
... Containment Pressure . The containment pressure used for evaluating cooling effectiveness during reflood and spray cooling shall not exceed a pressure calculated conservatively for this purpose . The calculation shall include the ...
... Containment Pressure . The containment pressure used for evaluating cooling effectiveness during reflood and spray cooling shall not exceed a pressure calculated conservatively for this purpose . The calculation shall include the ...
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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...