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Invention Report - Development of a Solution to Oxidize and Dissolve Uranium Metal and Its Oxides

Description: Decontamination of a high-temperature pressurizedwater reactor core- coolant recirculation system following a fuel element cladding failure requires the dissolution of uranium oxides + uranium metal. An oxalic--peroxide-peracetic solution was developed which was found to be superior to other solutions for this task. The solution composition is: oxalic acid, 2.3 g/l: sodium oxalate, 32.0 g/ l; hydrogen peroxide, 15.0 g/l; 8-quinolinol, 1.0 g/l; and 40% peracetic acid, 12.5 g/l. 8-Quinolinol suppresses the decomposition of H/sub 2/O/sub 2/ in steel vessels. Corrosion data indicate that, of all the structural materials tested, only brass and brass alloys are corronded to any extent by this solution. This solution was used in the decontamination of the Plutonium Recycle Test Reactor. (D.L.C.)
Date: December 31, 1962
Creator: Weed, R. D.
Partner: UNT Libraries Government Documents Department
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Reactor Branch monthly reports, January--December 1962

Description: This document details the activities of the Reactor Branch for the months of January through December of 1962. (FI)
Date: December 31, 1962
Creator: Plum, R. L.
Partner: UNT Libraries Government Documents Department
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Production of Void and Pressure by Fission Track Nucleation of Radiolytic Gas Bubbles During Power Bursts in a Solution Reactor

Description: The Kinetic Experiment on Water Boiler (KEWB) reactor is a 50-kw aqueous homogeneous research reactor which was designed to study the safety characteristics and dynamic behavior of this class of reactors. When the reactor is placed on a short-period power transient, its aqueous uranyl sulfate fuel solution becomes rapidly supersaturated with H/sub 2/ gas produced by the radiolysis of water. At a critical gas concentration, fission track nucleation of H/sub 2/ bubbles occurs. The rapid formation and growth of these bubbles creates a pressure field, the so-called inential pressure, which causes an increase in solution volume. This increase in solution volume, referred to as void, causes a loss of reactivity and constitutes an important shutdown mechanism. The conditions under which fission track nucleation of gas bubbles occurs are described. It is shown that the void volume and void compensated reactivity can be calculated from a knowledge of the pressure field. Simple models for the pressure field are presented which satisfactorily describe the observed pressures. The inpile capsule and KEWB experiments which confirm the validity of the mechanisms for these processes are described. The equations and data presented make it possible to predict with accuracy the onset and magnitude of the inential pressure and the dynamic reactivity for a large class of aqueous homogeneous reactors. (auth)
Date: December 30, 1962
Creator: Spiegler, P.; Bumpus, C. F., Jr. & Norman, A.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Technology Quarterly Progress Report, July-September 1962

Description: Aqueous zirconium fuel processing studies, directed at adapting the hydrofluoric acid process to continuous dissolution-complexing in order to increase the capacity of the ICPP process, resulted in two successful approaches to the complexing-feed adjustment step. Continuous in-line adjustment (conversion of uranium(IV) to uranium(VI) necessary for extraction) was accomplished in one minute or less at approximately 90 deg C; surges of dissolver product from the operating dissolver up to 1.9 times the flow sheet rate did not inhibit the oxidation of the uranium at this temperature. Batchwise mixing in air of dissolver product solution with complexer solution oxidized the uranium within two minutes at 23 deg C or higher. Further studies of continuous zirconium dissolution indicated that precipitation of uranium at the acid inlet can be a problem, probably because of local concentration gradients of free HF, which result in conditions of low uranium solubility. Control of dissolver acid composition by electrical conductance measurement appeared possible due to the linear relationship of conductance with acid concentration. Aluminum alloy dissolution rates in nitric acid were found to vary significantly, depending on the type and amount of alloying agent. Silicon, nickel, and copper in the alloy significantly decreased the dissolution rate. Batch dissolution times for standard test coupons ranged from 14 minutes for a high purity aluminum to 1400 minutes for an alloy containing 2.9 percent silicon. In the electrolytic dissolution of Nichrome in a bench-scale basket dissolver, the substitution of titanium for niobium as the anode basket material significantly reduced the contact resistance. Current interruption due to contact failure was essentially eliminated, and contact resistance on the titanium was sufficiently low that increasing solution resistance due to acid depletion became a major contributor to current decline as dissolution progressed. The indirect solution-contact electrolytic dissolution principle was further studied, producing data on electrode …
Date: December 28, 1962
Creator: Bower, J.R. ed.
Partner: UNT Libraries Government Documents Department
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HEAVY ELEMENT ISOTOPIC ANALYSIS OF UO$sub 2$ FUEL IRRADIATED IN THE VBWR. Report No. 1

Description: Slightly enriched UO/sub 2/ fuel, irradiated in the Vallecitos Boiling Water Reactor (VBWR), with exposures ranging from 100 Mwd/t to 3200 Mwd/t was analyzed for heavy element isotopic composition and compared with computed data. The primary objective of this program is to obtain improved data on the changes in nuclear characteristics with burnup of UO/sub 2/ fuel in a boiling water reactor. This information is important in both evaluating the economics of a given reactor design and also in providing a sounder physics basis for improving reactor designs to minimize the resuiting fuel costs. Uranium oxide pellets, with an enrichment of 2.8 atom percent, were analyzed at several axial positions along the fuel rod, spanning the void (steam fraction) range of 0 to 30%. The isotopic composition for each pellet was computed, utilizing a general fuel cycle depletion code. Results of the analysis of the comparison of the measured and computed data indicate that the total amount of Pu computed is consistently lower than that implied from the measurement by approximately 10%, and the percentage difference between the measured and computed data increases slightly with exposure. One rod was irradiated near a control rod which was approximately 25% inserted. As expected, since no control rod effects were included in the calcuiation, the measured data in that region of the rod shows a greater Pu production per Mwd/t than computed. Physical effects which might explain the small, but apparentiy consistent, differences between the measured and computed data were postulated. It is concluded that the observed differences are the result of a substantial underestimate of void fraction and small uncertainties in fuel exposure and cross sections. (auth)
Date: December 28, 1962
Creator: Hackney, M.R. & Ruiz, C.P.
Partner: UNT Libraries Government Documents Department
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Phase Transformations in Calcination of Nitrates of Aluminum, Stainless Steel, and Nichrome

Description: Earlier studies showed that low concentrations of boric acid inhibit the formation of alpha alumina in the fluidized calcination of aluminum nitrate wastes. Studies designed to determine the optimum concentration of boric acid and the relative effectiveness of phosphoric acid were performed by heating synthetic mixtures at moderate pressure; results indicared that they were equally effective at the same molal concentration. Differential thermal analysis of mixtures showed that the boric acid reacted with alumina below 183 deg C. Extraction of boric acid from selected samples indicated that the B was bonded (probably in a random manner, as in glasses) to the alumina rather than to Na, Additlon of fission products was studied, and no unusual effects were found. Transformation studies on calcination of stainless steel nitrates indicate that alpha iron oxide is formed even with the addition of moderate amounts of addltives such as boric acid, phosphoric acid, aluminum nitrate, or combinations of these. Rare earths are the most effective additive found. Similar studies on nichrome wastes indicate that nickel oxide (crystalline) is formed even with additives. The studies include heating of synthetic mixtures at moderate pressure, differential thermal analysis, and use of a laboratory fluidized calciner. (auth)
Date: December 28, 1962
Creator: Eding, H J; Huggins, M L & Brown, A G
Partner: UNT Libraries Government Documents Department
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Control of information on Columbia River

Description: This brief report (December, 1962) discusses the effect of effluents from the Hanford Production reactors on the water temperature of the Columbia River.
Date: December 27, 1962
Creator: Johnson, W. E.
Partner: UNT Libraries Government Documents Department
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Effect of a reactor fuel element failure on the Columbia River radionuclide concentrations at Pasco, Washington

Description: The failure of a fuel element cladding in one of the water-cooled plutonium production reactors permits the erosion of irradiated uranium metal by the cooling water which is normally disposed to the Columbia River. Monitoring systems at both the reactors and at their effluent basin outlets to the river continuously monitor these streams, and if major fission-products release occurs the coolant can be held in retention basins. In addition to these monitoring systems, a river monitor is located at the 300 area which continuously monitors the gross gamma activity of the Columbia River; however, its sensitivity to rupture debris is limited because of the relatively high background'' from the short-lived (n, {gamma}) produced radionuclides in the river. In making hazard assessments and in providing adequate monitoring techniques and equipment at down-river locations, it is essential to know what changes occur in fission and (n, {gamma}) produced radionuclides following release of rupture products to the river.
Date: December 27, 1962
Creator: Perkins, R.W.
Partner: UNT Libraries Government Documents Department
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Centrifugal Distortion Corrections to Calculated Thermodynamic Functions

Description: Complete parition functions for non-rigid rotators are obtained for the linear, spherical top, and symmetric top cases, From these are derived expression giving the corrections to the thermodynamic functions due to centrifugal distortion as functions of the rotational distortion constants D. Numerical examples are given for HCN, methane, and ammonia.
Date: December 26, 1962
Creator: McDowell, Robin S.
Partner: UNT Libraries Government Documents Department
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CORROSION EVALUATION OF STAINLESS STEELS EXPOSED IN ICPP HIGH-LEVEL RADIOACTIVE WASTE TANKS

Description: Several 300 series stainless steels were corrosion tested in raffinate storage tanks made of the same materials. After exposure to the rafflnate solutions for periods of up to seven years, maximum penetration rates of 0.1 mil/ yr were noted. (auth)
Date: December 26, 1962
Creator: Hoffman, T. L.
Partner: UNT Libraries Government Documents Department
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The effect of chemical additives and coating materials on the adsorption of radionuclide parent elements of aluminum surfaces

Description: Laboratory studies have been conducted under simulated reactor operating conditions to determine the effect of various chemical additives and coatings on the adsorption of trace elements on aluminum surfaces. Of the materials tested, silicate additives and organic ink coatings were by far the most effective, reducing the adsorption of arsenic and phosphorus tracers by as much as one to three orders of magnitude. The laboratory techniques and results are discussed.
Date: December 26, 1962
Creator: Perkins, R. W. & Robertson, D. E.
Partner: UNT Libraries Government Documents Department
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K-Reactor Retubing Program graphite temperature study

Description: A project has been proposed and the funds allocated for the replacement of the central zone aluminum process tubes at both K Reactors with smooth bore zirconium process tubes of approximately the same outside diameter as the original tubes. Associated with this project is the problem of relieving the present graphite stack distortion in the vicinity of the process tube channels and counteracting or prereliving, at this time, the expected graphite stack distortion that, will take place over the next ten years. Such relief becomes increasingly important when it is realized that long reactor life is required for the zirconium tubes in order to justify the cost of the project. This justification is also based upon the ability to charge normal sized, self supported fuel elements during the reactor life of the tubes. Relieving the restrictions in the graphite process channels caused by stack contraction will be done by removing localized portions of the graphite from the tube blocks and trunion blocks with a guided cutting tool. This immediately brings up the question of graphite temperatures and the presently imposed maximum graphite in temperature limits. Combined coring and graphite stark distortion could result in excessive graphite temperatures or localized hot spots. This graphite temperature study was undertaken to permit predicting possible temperature problems that might be associated with the restoration of graphite channel straightness since the timing of the overall project completion will not allow time for extensive testing to determine such problem areas.
Date: December 26, 1962
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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NBS Viscometer Calibrating Liquids and Capillary Tube Viscometers

Description: Report discussing measurements of viscosity made with relative viscometers. These instruments must be calibrated with liquids whose viscosities are known. NBS provides a series of 10 oils for this purpose. Their viscosities range from 0.02 to 450 poises and their temperature coefficients of viscosity range from 2.1 to 9.4 percent per degree C. The less viscous oils are more stable. Correction formulas for errors or conditions are presented.
Date: December 26, 1962
Creator: Hardy, R. C.
Partner: UNT Libraries Government Documents Department
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Special review of selected reactor construction, operation, and program data

Description: This report documents the answers to specific questions posed by management on December 17,1962. The questions asked were: (1) What were the design and construction start and completion dates of project CG-558-600?, what was the percent power level increase design for CG-558-600?, what was the actual power level increase achieved?, what was the construction completion date of DR reactor?, what was the expansion-overbore program initiation date?, on what date was the oral overbore-type proposal made to HOO-AEC?, when was the initial documentation of overbore-expansion program?, on what dates were the budgets submissioned for the Reactor Modification Program?, what is the conversion ratio increase from the RMP?, what is the production capacity increase from the RMP?, and what are the design completion dates for the H, C, DR, and K reactors?. (GHH)
Date: December 26, 1962
Creator: Ballowe, J. W.; Brasfield, R. L. & Fifer, N. F.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: November 1962

Description: This report, from the Chemical Processing Department at HAPO for November 1962, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; and weapons manufacturing operation.
Date: December 21, 1962
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Operation support plan

Description: No Description Available.
Date: December 21, 1962
Partner: UNT Libraries Government Documents Department
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Development test No. IP-558-T Gas Sampling Facility correlated with front to rear thermocouple stringer: KW Reactor

Description: The test detailed in this report authorizes the installation of sampling tubes in the vacant-positions in one of the two front-to-rear graphite stringers to be installed in KW Reactor in January 1963. These lines will permit withdrawal of a gas sample from the active zone at a point where the graphite temperature is being measured. Analysis of this gas sample on the gas chromatograph and on a new catalytic oxygen-hydrogen instrument is expected to yield valuable information on graphite burnout versus temperature and gas quality.
Date: December 20, 1962
Creator: Cooke, J. P. & Baars, R. E.
Partner: UNT Libraries Government Documents Department
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