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Single tube meltdown incident

Description: In connection with design of rear face fittings for the plant-expansion study currently being conducted we have been asked to determine if rear face pressurization is required for safety reasons and if so, how much. Pressurization of the rear face piping would be used to provide sufficient reverse flow to prevent process tube burnout in the event of complete loss of coolant supply to a single tube by virtus of a front connector failure. Consideration of the effectiveness of rear face pressurization, however, requires a more general look at the problem of single tube meltdown than that provided by considering front fitting failure alone.
Date: February 1, 1960
Creator: Trumble, R. E.
Partner: UNT Libraries Government Documents Department
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Recovery of Neptunium From Purex Waste by an Agitated Bed of Anion Exchange Resin

Description: Technical report. From Abstract: "Data are presented for the absorption of thorium and neptunium from synthetic waste concentrate of the "Purex" process by a miniature agitated bed of anion exchange resin. The behavior of neptunium indicated that efficient recovery should be obtained from Purex high activity waste concentrate by this technique. A method was developed for calculating absorption losses from agitation beds of resin. The predicted losses were in excellent agreement with experimental results."
Date: February 1960
Creator: Prout, William E., 1921- & Fernandez, LeVerne P.
Partner: UNT Libraries Government Documents Department
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Physics Data From a Mockup of the HWCTR Lattice in the PDP

Description: Technical report. From Abstract: "Experiments were performed in the Process Development Pile (PDP) with a critical mockup of the Heavy Water Components Test Reactor (HWCTR) lattice. Reactivity measurements served to determine control rod worths, the temperature coefficient of the reactor at low temperatures, the dependence of keff on concentrations of U235 and poisons in the "driver" region of the reactor, and the changes in keff that occur in certain conceivable accidents in the HWCTR. Flux distribution measurements were made to determine over-all flux shapes, local flux variations around individual components, azimuthal flux variations due to asymmetrical combinations of control rods, and vertical flux variations obtainable through the use of control rods of partial length. Sufficiently detailed flux measurements were made to permit the calculation of neutron economy tables and to determine the neutron leakage from the reactor. Suitable adjustments in the input parameters made it possible to fit the experimental results with a two-group calculation."
Date: February 1960
Creator: Graves, William E.
Partner: UNT Libraries Government Documents Department
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ETR Nuclear Instrumentation : Final Report

Description: Report regarding the primary nuclear instrumentation at the Engineering Test Reactor (ETR) and early difficulties.
Date: February 3, 1960
Creator: Hanson, D. C.
Partner: UNT Libraries Government Documents Department
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Radiations from nuclear weapons - signal detectors - NASA program information

Description: This letter is for the purpose of supplying the information that you requested at the meeting of the sub-committee on Project Vela. It is divided into three parts: (1) Radiations from nuclear weapons; (2) Backgrounds for Vela Signal Detectors; (3) Discussion of the NASA program.
Date: February 10, 1960
Creator: White, R. S.
Partner: UNT Libraries Government Documents Department
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Anion Exchange Recovery of Plutonium From Reduction Residues

Description: Technical report. From Abstract: "An anion exchange process was demonstrated for the recovery of plutonium from waste produced in the reduction of plutonium salts to the metal. Plutonium in a highly salted 6M nitric acid solution derived from the dissolution of slag and crucible waste was separated from impurities by absorbing the Pu (IV) nitrate complex on the anion exchange resin and subsequently eluting with nitric acid. A flowsheet for plant operation is presented."
Date: February 1960
Creator: Russell, Edwin R.
Partner: UNT Libraries Government Documents Department
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Reactor hazards review zirconium retubing of Hanford reactors

Description: This report examines the pertinent features in the hazards analyses of the Hanford Reactors which may be affected by the substitution of zirconium tubes for the present aluminum process tubes. Resized I & E slugs, designed to preserve present pressure drops across the active zones and to minimize corrosion, are used as examples to compare the characteristics of the zirconium tubes reactor with the present.
Date: February 15, 1960
Creator: Nilson, R.
Partner: UNT Libraries Government Documents Department
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100-K Area electrical power system load and voltage study for project CG-775. Revision

Description: The proposed increased water capacity for 100-K plants will increase the electrical load to be supplied. The load study showed that the capacity of the existing 13.8 kV system is adequate to carry the increased loads proposed for Project CG-775, while for the 5 kV system, an expanded power system is proposed. Likewise, the voltage regulation on the kV system bus will be excessive, and voltage regulators should be added.
Date: February 22, 1960
Creator: Thorson, W. R.
Partner: UNT Libraries Government Documents Department
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Fuel element handling before irradiation

Description: This report on fuel element handling presents in some detail the current status of an engineering study which has been underway for some time, and which is continuing. The study was undertaken to determine if it is feasible, and if it is practicable, to revise the method and equipment used for fuel element handling with existing charging machines.
Date: February 1, 1960
Creator: Gilbert, R. D.
Partner: UNT Libraries Government Documents Department
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Recommendations to apply the ``square pile`` total control concept

Description: It is recommended that the ``square pile`` concept be adopted for all disaster total control calculations, and that the basic reactor constants listed in HW-62884, except for Ball 3X local strength at the DR Reactor, be used in applying this method. Curves are included for each reactor type, indicating allowable enrichment based on appropriate local control strengths. (The reactors whose operating methods are affected by disaster total control requirements are B, D, F, and DR Reactors; the remaining piles have sufficient geometrical coverage). An example of the analytical method is included.
Date: February 25, 1960
Creator: Bowers, C. E.
Partner: UNT Libraries Government Documents Department
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Rear crossheader fitting inspection B, D, and F Reactors

Description: Cavitational flow has been known to exist in-rear crossheader ``Parker`` fittings at B, D, and F Reactors for the last five or six years. Calculations showing initiation of cavitational flow as a result of high flow rates in the present fittings were verified by experimental data in 1954. A study is currently being conducted to determine the required plant modifications to obtain flow increases on the order of fifty percent above existing flows. This study and the results of preliminary tests that show nominal flow increases may be obtained by reaming rear crossheader fittings has focused attention on the condition of existing rear face piping. To obtain an estimate of the effect of cavitation in rear crossheader fittings resulting from past and current operating conditions, twenty one fittings were examined during the period October 6, 1959 to November 30, 1959. This document reports the inspection results.
Date: February 10, 1960
Creator: Kempf, F. J.
Partner: UNT Libraries Government Documents Department
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Precise Measurement of Heat of Combustion with a Bomb Calorimeter

Description: From Introduction: "This Monograph describes methods and apparatus used at the National Bureau of Standards in connection with several series of investigations of heats of combustion of aircraft fuels [4, 5, 6, 7]."
Date: February 26, 1960
Creator: Jessup, R. S.
Partner: UNT Libraries Government Documents Department
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Production of cobalt-60

Description: Cobalt samples frequently are irradiated in nuclear reactors to produce gamma sources and can be irradiated as integral flux monitors because of the long half-life of the isotope produced. At the present time a small cobalt sample is being irradiated within the KW Reactor Snout facility for future use as a radiographic source for inspection of finished product in the Chemical Processing Department. Analysis was made to estimate the buildup of activity in this sample; the general equation may be of interest and value for other cobalt sample irradiations.
Date: February 29, 1960
Creator: Bunch, W. L.
Partner: UNT Libraries Government Documents Department
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Energy release per fission in the Hanford reactors

Description: The average energy release per fission event in a reactor is dependent on the composition and arrangement of the lattice materials. In a study of heat generation in the NPR, Nilson developed expressions for calculating the average energy released in each material per fission event. These relationships have been used in the present calculations to obtain the energy release per fission in existing Hanford reactors.
Date: February 12, 1960
Creator: Morgan, W. C. & Bunch, W. L.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly record report, January 1960

Description: This document details activities of the irradiation processing department during the month of January 1960. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: February 19, 1960
Partner: UNT Libraries Government Documents Department
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Use of poison splines to reduce non-equilibrium losses, KE Reactor

Description: A significant reduction in non-equilibrium losses is possible through the use of poison splines for reactivity and heat distribution control during reactor startups. The curves presented show the results of an analysis of recent KE Reactor poison spline startup usage. These curves demonstrate the magnitude of gains possible at other reactors through the use of poison splines for turnaround control.
Date: February 5, 1960
Creator: Franklin, F. C.
Partner: UNT Libraries Government Documents Department
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Rezoning of fringe at 105-KE Reactor

Description: A study was made to determine the optimum arrangement of the fringe flow zones at KE Reactor. Also considered, was the possibility of converting part or all of the existing fringe zone (actually three flow zones) from solid metal to I & E metal to decrease rupture potential in these low flow zones. The necessity for this study was indicated by high tube outlet temperatures in the fringe flow zones and the recent occurrence of two solid metal ruptures in process tubes located in the fringe zone of the reactor. Two additional solid ruptures occurred during the period that conversion to I & E in zone 2, as recommended below, was being completed.
Date: February 26, 1960
Creator: Leitz, E. E.
Partner: UNT Libraries Government Documents Department
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Extended hydraulic demand curves for K geometry tubes with I&E fuel elements

Description: Steady state hydraulic demand curves were obtained for tube powers of 500, 1000, 1500 and 2000 KW with an inlet water temperature of 20C and a rear header pressure of 25 psig. These curves are shown in figures. The point of initial unstable flow for various tube powers is shown for a front header pressure of 325 psig. The flow rate that would lead to the initial point of unstable flow as a result of a sudden plug upstream of the Panellit tap is shown in a figure.
Date: February 25, 1960
Creator: Hesson, G. M.; Fitzsimmons, D. E. & Kanninen, M. F.
Partner: UNT Libraries Government Documents Department
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Effect of increased nickel content in canning baths

Description: Canning bath Al-Si, supplied from offsite vendors and reclaimed lathe turnings in the 313 building, is used in the production of I & E fuel elements. A study was made of the effect of increasing the Ni content to over 0.5% in the canning baths, in order that all of the X-8001 scrap could be reclaimed. Effect on bond quality, weld integrity, and canning bath operation was studied. Based on adverse weld quality, slight loss in reactivity, and potential for furnace channel plugging, it is recommended that the present Ni specification of 0.5% maximum remain unchanged.
Date: February 2, 1960
Creator: Strand, C. A.
Partner: UNT Libraries Government Documents Department
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Laboratory determination of normal operating flow rates with the 105-F rear face floating nozzle

Description: A new rear nozzle has been developed by Mechanical Development (A), IPD to alleviate the stuck gun barrel problem on the process tubes at F reactor. This nozzle is called the 105-F rear face floating nozzle (RFFN) and is shown in Figure 4. The purpose of this study was to determine the hydraulic operating characteristics of this nozzle and to compare these characteristics with those of the standard nozzle assemblies. This report is essentially an addendum to EW-63756 1 which presented energy loss data for various outlet fitting assemblies for possible use on the BDF type reactors The experimental data for this study were obtained with the use of the hydraulics mockup in the 189-D Thermal Hydraulics Laboratory.
Date: February 17, 1960
Creator: Findlay, J. A.
Partner: UNT Libraries Government Documents Department
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Interim evaluation of nickel plate on aluminum-jacketed fuel elements

Description: Nickel plating on the coolant contacting surfaces of aluminum-jacketed fuel elements is highly attractive for increasing resistance. Potential benefits include a highly corrosion-resistant coating for severe localized conditions, reduction of mechanical damage to fuel element jackets, improved fuel element alignment (by reducing friction between fuel element and process tube ribs) and probably lower overfall surface temperatures to reduction in corrosion product film with improved corrosion resistance, neutron economy might also be realized. For example, substitution of a 0.5 mil thick nickel plate for 15-mils thickness of aluminum jacket would result in no reactivity loss and permit a concomitant increase in uranium volume, or in coolant flow annulus. Attendant problems include providing an adherent continuous plate of uniform thickness and possibly contamination of reactor effluent by radio-nickel-cobalt, and phosphorous and it was found that gross sloughing of the nickel plate had occurred. Development and testing work was carried out to determine the cause and a solution to the Greece problem. Studies were limited to the behavior of chemically-deposited nickel because of the unique capability of the process to deposit a coating of uniform thickness in the 0.1 - 0.2 mils thick range, regardless of the geometry of the plated piece. Based on ex- reactor tests, a readily applicable method for significantly improving plate adherence has been developed, as summarized in this report.
Date: February 8, 1960
Creator: Jacky, G. F.
Partner: UNT Libraries Government Documents Department
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Hazards survey 1706-KER Recirculating Test Facility

Description: This report presents the results, conclusions and recommendations of a comprehensive study of the hazards potential of the 1706-KER in-pile recirculation loops, Although more data are needed to verify or refute certain tentative conclusions, the general conclusion of this report is: with the exception of severe coolant loop rupture incidents, especially process tube ruptures, the loops will not possess serious hazards potential when they are operated within the limits specified in the Process Standards as amended by the acceptance of the recommendations of this report concerning the pressurizer vent system and the process tube exit trips. The potential for fuel burnout or meltdown following a coolant loop rupture should be reduced considerably after completion of Project CGI-839, ``Modification to Fuel Element Test Facilities.`` The present potentially ``worst case`` coolant loop rupture could lead to an accident comparable in severity to a single K-Reactor tube rupture and meltdown. Serious personnel and property contamination would be confined to the vicinity of the reactor following completion of Project CGI-791, ``Reactor Confinement`` unless unusual atmospheric conditions persisted during the entire release time, i.e., strong, unidirectional winds causing rapid straight-line, non-mixing travel of the fission products plume. However, graphite stack damage from a tube rupture could be severe and costly. Coolant system reliability criteria for non-production facilities located in Hanford production reactors are now being prepared. In the absence of such criteria, the Reactor Coolant Supply System Reliability Criteria were applied to the KER loops in this report. However, it should be noted that, if the proposed non-production facilities criteria are accepted in their present form, the basic statements concerning the adequacy of the KER loops` coolant systems given in this report will not be altered significantly.
Date: February 4, 1960
Creator: Norwood, K. W.
Partner: UNT Libraries Government Documents Department
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