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Description: The economics of waste disposal by pit storage when the geological location of the pits does not coincide with the location of the processing plant are considered. Optimum cooling times before shipment were determined for 250gallon batches of Purex-type waste. Three distances between processing and disposal sites, and three unit storage costs were considered. It was concluded that as the storage cost increases it becomes economical to ship shorter-cooled waste, and as the shipping distance increases, it becomes economical to store waste longer. In the case of 30/gal/yr storage, for 200 miles shipment, essentially no storage should be provided beyond that required for surge in filling carriers. For less highly irradiated material, the optima would shift in the direction of shorter cooling times. Data are tabulated and presented graphically. (C.H.)
Date: October 24, 1955
Creator: Zeitlin, H.R. & Ullmann, J.W.
Partner: UNT Libraries Government Documents Department

Reactor Development Quarterly Progress Report

Description: The design and construction program of the Bolling Experimental Reactor is reviewed. A number of preliminary experinnents were performed with Borax-II at pressures between 75 and 300 psi. The most corrosion-resistant U-Zr--Nb alloy developed so far is produced by heating in a vacuum to the gamma phase, quenching, and aging for 2 hr at 400 deg C. Special attention is given to the removal of H/sub 2/ from the material. Unclad and unirradiated samples of U--Nb and U--Nb--Zr alloys were corrosion tested in H/sub 2/O. Corrosion rates were also measured under irradiation conditions in CP-5. Elongation measurements of irradiated wrought and cast U--Zr material suggested no way for treating the wrought fuel so that stability comparable to the cast material could be obtained. Natural circulation boiling density tests at 600 psia were made in order to determine the effects of channel cross section and subcooling on the steam void fraction. Results of autoclave and dynamic corrosion studies of 2-S Al in H/sub 2/O are reported. These results include the testing of Ni-clad samples. A large number of criticality calculations were performed for the EBR-Il and the PBR. The solubility of ThO/sub 2/ pellets containing various concentrations of U/sub 3/ O/sub 8/ was tested in water at 316 deg C for periods of 672 to 744 hr. None of the samples disintegrated, although at least one sample developed cracks. Solutions of reactor kinetic equations were attempted for the purpose of studying transients in reactors with lifetimes of 7 x 10/sup -9/ 10/sup -7/, and 6 x 10/ sup -5/ sec. Ignition experiments were performed on Th, Cu, Al, Fe, Mg, Zr, and fluorothene when contacted with fluorides. Except for Zr and fluorothene, the materials did not ignite. (C.H.)
Date: January 31, 1955
Partner: UNT Libraries Government Documents Department


Description: The status of Experimenial Boiling Water Reactor development is reviewed. Shell testing, control mechanism development, fuel corrosion, and dimensional stability studies, and design consideration to facilitate D/sub 2/O operation are discussed. Fuel plate and subassembly fabrication, corrosion, and radiation damage studies were continued. Reactor water filtration, purification, and induced activity are considered. High-temperaiure operational tests were run on Experimental Breeder Reactor mechanisms. Though several minor malfunctions were encountered, the basic operation is considered satisfactory. Studies of the physical and metallurgical properties of U -- Mo, U - Zr, U -- Pu, and U -- Pa -- Mo alloys for fuel elements were conducted. Conversion ratio deiermination for the second loading of EBR-I gave a value of 1.03 plus or minus 0.05. Alloys and systems w-ere irradiated anci the effects of the irradiation on corrosion determined. Included in the irradiation were U, U - Si, Nb - Sn, UO/sub 2/, and Al - Ni. (For preceding period see ANL-5476.) (D.E.B.)
Date: October 31, 1955
Creator: McLain, S. comp.
Partner: UNT Libraries Government Documents Department


Description: This design study describes a reactor and associated power plant that has been designed to produce 100 kv of net electric power and 400 kv of hot water space heating at a total thermal output of 1300 kw. The fuel consists of a solution of UO/sub 2/SO/sub 4/ in light water. Power is removed from the core by boiling the fuel solution and transferring the heat to the secondary steam system by condensing primary water on the external surface of a bayonet type boiler and boiling secondary water within the tubes. Saturated steam, produced in the boiler at 225 psia (Full Power) is used to drive a turbo generator, Extraction steam from the turbine is used, at a reduced pressure, for space heating. The initial loading of the reactor is approximately 4.8 kg of U/sub 235/ and operation based on an average load factor of 80% will require fuel addition at the rate of about 580 grams per year. It may be desirable to replace the fuel in the core after a period of 5 years operation due to the accumulation of corrosion products. The reactor control is affected automatically by power demand. The major objective has been to design a reactor that is reliable and simple, requiring little if any operating personnel and routine maintenance only which can be performed by one man. The design should stress simplicity of the system, ease of erection at the site, initial transportability, reliability and ease of operation; these characteristics are then expected to result in greatly reduced effort and manpower support over a conventional system. (auth)
Date: June 1, 1955
Creator: Mong, B.A.; Colgan, J.E.; D'Elia, R.A.; Mooradian, J.S.; Rhode, G.K. & Wood, P.M.
Partner: UNT Libraries Government Documents Department


Description: 8 5 6 2 0 5 8 5 5 ? 5 : tion of the HRT is summarized. The design of some reactor components is described, including fuel system line coolers, the thermal shield, instrument cubicles, the reactor cell air monitor, and sampling facilities. The important design specifications for the HRT fissionproduct adsorption system are outlined. The effects of fluid circulation on HRT stability, the results of the rupture of the fuel inlet nozzle on the pressure vessel, core tank temperature, and heat generation and temperature distribution in the control room area shield were examined. Operation of the HRT mockup loop is summarized. High generalized corrosion rates and U precipitation were observed when 50 ppm oxygen was used. Results from tests of HRT pumps, heat exchanger, sampler mockup, and reflex condenser and recombiner are presented. Design of the instrumentation in the control room area and fabrication of differential pressure and liquid level transmitters are reported. Thorium Breeder Reactor. Stability criteria, the effect of slurry settling on reactivity, and neutron losses due to coating the core tank with platinum bave been analyzed for the TBR. An economic study of partial fuel costs for one-region Pu-U reactors was completed. The design concept of a 300- electrical-Mw thorium breeder power station utilizing low-pressure gas recombination was completed, and construction and operating costs were estimated. Design problems which must be solved before the design can be considered practical are discussed. Medification of TBR design from low- to high-pressure recombination was started. Corrosion. Operation of dynamic-corroslon test loops with uranyl sulfate solutions and thorium oxide slurries proceeded in a routine manner, and results are presented tabularly. Sedimentation characteristics of thorium dioxide slurries were determined at 100 to 300 deg C. Development, fabrication, and operation of in-side loops for radiation corrosion studies are described. Data from ...
Date: August 1, 1955
Creator: McDuffle, H.F. & Kelly, D.C. comps.
Partner: UNT Libraries Government Documents Department