Fuel Cycle Program A Boiling Water Reactor Research And Development Program Third Quarterly Report January 1961 March 1961
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Fuel Cycle Program A Boiling Water Reactor Research And Development Program Third Quarterly Report January 1961 March 1961
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Author :
language : en
Publisher:
Release Date : 1961
Fuel Cycle Program A Boiling Water Reactor Research And Development Program Third Quarterly Report January 1961 March 1961 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with categories.
The continuing analysis of the VBWR core resulted in refinements in the calculations for reactivity in voids, flux leakage and resonance escape probability. The Zircaloy cladding for 25 fuel assemblies was received and passed inspection. Preliminary measurements of VBWR flux oscillations, used to develop instrumentation and data interpretation techniques, showed random normally-distributed oscillations with a predominant frequency of 0.5 to 1.0 cycles/second. A model for analog computer simulation of a reactor as a feedback control system was adapted to VBWR. Equations for the hydraulics model and preliminary results from use of the model are presented. Irradiation of the Fuel Cycle stainless steel clad assemblies reached 412 MWD/T with specific powers of 28 kw/kg (average) and 52 kw/kg (peak) during January. Visual examination of the fuel after this irradiation indicated that it is in good condition. The VBWR was shut down during February and March for replacement of all in-core components made of 17-4 pH stainless steel with 304 stainless steel. The details of the first eight special fuel assemblies were determined and materials were ordered. The effects of steam quality, mass flow rate, and rod diameter on burnout heat flux are shown. The burnout heat flux varied inversely with mass flow rate; this result was contradictory to several previous correlations. The experimental phase of the high-pressure observational boiling experiment was completed. Reproducibility of the burnout points was good (about plus or minus 1 1/2%). High speed movies of the flow conditions at burnout are being analyzed. (auth).
Fuel Cycle Program A Boiling Water Reactor Research And Development Program
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Author :
language : en
Publisher:
Release Date : 1961
Fuel Cycle Program A Boiling Water Reactor Research And Development Program written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with Boiling water reactors categories.
Fuel Cycle Program A Boiling Water Reactor Research And Development Program
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Author :
language : en
Publisher:
Release Date : 1960-08
Fuel Cycle Program A Boiling Water Reactor Research And Development Program written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1960-08 with Boiling water reactors categories.
Power Reactor Technology And Reactor Fuel Processing
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Author :
language : en
Publisher:
Release Date : 1963
Power Reactor Technology And Reactor Fuel Processing written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1963 with Nuclear engineering categories.
Heavy Water Moderated Power Reactors
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Author :
language : en
Publisher:
Release Date : 1962-10
Heavy Water Moderated Power Reactors written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1962-10 with Heavy water reactors categories.
Nuclear Science Abstracts
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Author :
language : en
Publisher:
Release Date : 1974
Nuclear Science Abstracts written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1974 with Nuclear energy categories.
Power Reactor Technology
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Author :
language : en
Publisher:
Release Date : 1963
Power Reactor Technology written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1963 with Nuclear engineering categories.
Atomic Energy Research Reports For Sale By The U S Department Of Commerce Office Of Technical Services
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Author : Business and Defense Services Administration
language : en
Publisher:
Release Date : 1963
Atomic Energy Research Reports For Sale By The U S Department Of Commerce Office Of Technical Services written by Business and Defense Services Administration and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1963 with categories.
Fuel Cycle Program A Boiling Water Reactor Research And Development Program Eleventh Quarterly Progress Report January March 1963
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Author :
language : en
Publisher:
Release Date : 1963
Fuel Cycle Program A Boiling Water Reactor Research And Development Program Eleventh Quarterly Progress Report January March 1963 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1963 with categories.
Even though VBWR shutdowns were required for location and removal of five failed fuel assemblies (HPD Program), the increase in fuel exposure was good. Fuel exposures wili pass the values at which cold worked stainless steel cladding was failing under the HPD Program. Failure of the 0.005-inch cold worked stainless steel clad fuel rods in assembly 8L was traced to strain cycling fatigue. A study of tapered fuel rods indicates a potential advantage for us of a variable water/fuel ratio along the flow channel. Natural circulation tests in the hydraulic stability loop were conducted over a range of conditions from stable, to oscillatory with exponential decay, to self-sustaining oscillation of constant amplitude, to unstable oscillations with divergent amplitude. The response to impulses in power input shows the effect of the time delay for transporting steam voids up through the riser. The data permit calculation of oscillation frequency, damping coefficient, time lags, and show the magnitude and character of pressure and velocity changes. The data, which have an experimental scatter of plus or minus 10% maximum, show that burnout heat fiux: decreases with increasing flow up to 2 x 108 lb/hr-ft2; has a maximum for hydraulic diameter between 0.25 and 0.5 inch; and decreases for pressure increases between 600 to 1400 psi. A correlating equation for the data is given. The data are compared to results of others. Tests of special geometries show that the burnout heat flux: decreases 22 to 50% when the heated rod is within 0.033 inch of the channel wall; is unchanged upstream of a plate-type spacer; decreases 35 to 50% when the rod surface is roughened by sandblasting; is increased 20 to 40% by use of a rough liner. The four-rod test section is operating satisfactorily and 17 critical heat fiux data points are obtained at 1000 psia and flows of 0.5, 1.0, and 1.5 x 106 lb/hr-ft2. In each case the critical heat flux occurred at the exit end and on the side of the rod facing the corner of the channel. The evaluation of film trippers (rough liner) on the unheated channel walls indicates considerable promise for increasing the burnout heat flux limit. The theory of operation is that the liquid film on the unheated wail is sheared off and dispersed, thus adding to the liquid film on the heated rod. Measurements with a heater rod bowed so that it is in contact with the channel wall show that the critical heat flux is decreased by a factor of two or more from values with normal clearance. Temperature measurements on the rod, when operating past the critical heat flux, were in the order of magnitude of 1000 deg F for heat fluxes of about 500,000--600,000 Btu/hr-ft2. Chemical analyses for radial variations in isotopic composition within a fuel pellet are nearly completed and are compiled for interpretation. (N.W.R.).
Experience With Stainless Steel As A Fuel Cladding Material In Water Cooled Power Reactor Applications
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Author : T. J. Pashos
language : en
Publisher:
Release Date : 1963
Experience With Stainless Steel As A Fuel Cladding Material In Water Cooled Power Reactor Applications written by T. J. Pashos and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1963 with Metal cladding categories.