Resource Type

Proposed R.F. Buncher for A-12 (open access)

Proposed R.F. Buncher for A-12

A buncher and pre-accelerator for A-12 is described that has 360 degree acceptance and could handle a current of one ampere from a low voltage source.
Date: June 25, 1952
Creator: Colgate, S. A.
System: The UNT Digital Library
In-Core Instrumentation Development Program Quarterly Progress Report June - September 1963 (open access)

In-Core Instrumentation Development Program Quarterly Progress Report June - September 1963

Introduction: The objective of Project Agreement 22 is to determine the feasibility of covering the complete reactor neutron flux start range from 10(3) - 5 x 10(13) nv by using in-core chambers. The counting mode of operating will be used at low neutron fluxes and the root mean square voltage fluctuation mode will be used at high neutron flux levels. Experiments have been run utilizing various ion chambers, gases, gas pressures, voltage, and cables to measure sensitivities and range operating in the counting and RMS voltage modes. Theoretical discussions are presented showing how the RMS voltage is related to individual pulse at both amplifier input and output. Noise is also compared at amplifier output so that the optimum bandwidth can be selected. Spectral shifts with changes in applied voltage causing signal variations have been examined and can be eliminated by appropriate selection of amplifier bandwidth. In the counting mode, all experiments have been conducted with unterminated cable. The chamber has been designed with geometry, gas, and pressure to completely stop fission fragments in the gas and hence maximize the charge generated in the chamber. Cables have been selected to minimize capacity. Various gases, pressures, and voltages have been used to …
Date: October 1963
Creator: DuBridge, R. A.
System: The UNT Digital Library
In-Core Instrumentation Development Program Quarterly Progress Report September - December 1963 (open access)

In-Core Instrumentation Development Program Quarterly Progress Report September - December 1963

Introduction: The objective of Project Agreement 22 is to determine the feasibility of using in-core ion chambers to cover the complete reactor neutron flux startup range from 10(4) -5 - 10(13) nv using in-core ion chambers. The counting mode of operation will be used at low neutron flux levels and the RMS voltage fluctuation mode (Campbell Theorem) will be used at high neutron flux levels. The June-September Progress Report (GEAP-4386) shows how the RMS voltage mode can be used, discusses counting problems with long cable and ways of maximizing signal levels. This report discusses primarily the effect of gamma on counting with in-core ion chambers and the range of neutron flux measurable in the RMS voltage mode. Readers are referred to GEAP-4386 for a summary of all previous progress to attain the objective of PA-22.
Date: January 1964
Creator: DuBridge, R. A.
System: The UNT Digital Library
Mechanical, Fluid Flow, and Heat Transfer Out-Of-Pile Tests on EVESR MKI Prototype Fuel Bundle (open access)

Mechanical, Fluid Flow, and Heat Transfer Out-Of-Pile Tests on EVESR MKI Prototype Fuel Bundle

Summary: An EVESR MKI prototype fuel bundle was fully instrumented and operated intermittently for a 5-month period at the Pacific Gas and Electric Company’s Moss Landing Power Station. The vessel was operated up to 1000 psi with steam flows from 3000 to 26,600 lb/h, and steam inlet temperatures up to 825 degrees F. Data was recorded for blowout, vibration, flow distribution, heat transfer and pressure drop. The mechanical integrity of the fuel bundle, riser, and jumper system was satisfactory and considered to be of adequate design. No significant vibrations were noted during the various phases of operation. Average flow distribution in three of the inner tubes showed an average variation of 5 percent from equal distribution. The center and corner tubes were low and the side tube was high. Maximum deviation, from an equal one, measured 12 percent. Blowout of the flooded fuel bundle was accomplished with dry or significantly wet 1000 psia inlet steam, that steadied out to a minimum flow of 1250 lb/h. Blowout times were estimated at less than a minute for all flows above 1250 lb/h, and times in the vicinity of 2000 lb/h were estimated to be in the order of 5 to 15 seconds. …
Date: February 1964
Creator: Polomik, E. E.; Fritz, J. R. & Ianni, P. W.
System: The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Eighteenth Quarter, November, 1963-January, 1964 (open access)

Nuclear Superheat Quarterly Project Report: Eighteenth Quarter, November, 1963-January, 1964

From introduction: "This is the eighteenth in a series of quarterly reports which cover the progress and results from the conceptual designs, economic evaluations and research and development work performed by the General Electric Company as part of Contract AT(01-3)-189, Project Agreement No. 13."
Date: February 15, 1964
Creator: Flock, W. L. & Imhoff, D. H.
System: The UNT Digital Library
Preoperational Power Stability Analysis of the Consumers Big Rock Point Plant (open access)

Preoperational Power Stability Analysis of the Consumers Big Rock Point Plant

Summary: An analytical study of the stability of the Big Rock Nuclear Reactor has been performed for the plant as built, and supplements a previous design stability study. The plant has been determined by this analysis to be very stable under every mode of operation anticipated during Phase I of the development program testing. Even under conservative assumptions of system parameters the minimum calculated gain and phase margins do not go below 13.0 db and 46 degrees, respectively. (Nor are these both reached simultaneously for the same operating condition.) These are characteristics of a very stable, well-behaved system. In addition to this analysis, a second, less conservative series of computations was performed to provide expected realistic closed loop data for comparison with Phase I test results. The most responsive test thus predicted occurs at 60 percent power, 1500 psia, minimum flow, and maximum subcooling. For this case the closed loop peak response of power to reactivity occurs at a frequency of 0.90 cycles per second with an amplitude of 3.90 db. This corresponds to an expected open loop gain margin of 16.5 db and a phase margin of 63 degrees. Although knowledge of reactor transfer function is to be determined …
Date: February 1964
Creator: Case, J. M.
System: The UNT Digital Library
Two-Phase Pressure Losses Quarterly Progress Report: Eighth Quarter, November 12, 1963 - February 11, 1964 (open access)

Two-Phase Pressure Losses Quarterly Progress Report: Eighth Quarter, November 12, 1963 - February 11, 1964

Technical report describing that voids were measured in a ½-inch by 1-3/4-inch channel with the S-1 insert (B(0)/B(1) = 0.4, L(0) = 0.1 inch), at 2 inches ahead of the insert (position A), ½-inch past the insert (position B), 5 inches past (position C), and 12 inches past (position D). The conditions were: P – 1000 psia, G = 1.00 x 10(6) lb/h-ft(2), and x = 18.8 percent. Average void and void distribution at position A are the same as for flow in a straight channel. Void distribution at position B shows that the stagnation region downstream of the inserts contains a high fraction of voids. Average void and void distribution at positions C and d show that the two-phase mixture becomes strongly mixed (homogenized) as a result of passing through he contraction-expansion inserts. Distribution at position D approaches the distribution at position A; i.e., the straight channel distribution.
Date: March 1, 1964
Creator: Janssen, E. (Engineer) & Kervinen, J. A.
System: The UNT Digital Library
High Power Density Development Project: Sixteenth Quarterly Progress Report, January-March 1964 (open access)

High Power Density Development Project: Sixteenth Quarterly Progress Report, January-March 1964

Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC. Five tasks are in progress: (1) Task 1A-High Power Density Fuel Development, (2) Task 1B-Fuel Fabrication Development. Assembly, (3) Task II-Stability, Heat Transfer and Fluid Flow, (4) Task III-Physics Development, and (5) Task IV-Co-Ordination and Test Planning.
Date: April 1, 1964
Creator: Holladay, R. L.
System: The UNT Digital Library
In-Core Instrumentation Development Program Quarterly Progress Report January - March 1964 (open access)

In-Core Instrumentation Development Program Quarterly Progress Report January - March 1964

The objective of Project Agreement 22 is to determine the feasibility of using in-core ion chambers to cover the complete reactor neutron flux startup range from 10(4) -5 - 10(13) nv using in-core ion chambers. This technical report discusses the following topics: low versus high cable termination impedance, amplifier considerations, noise considerations, gas and pressure selection, cable selection, effect of gamma, effect of temperature, and remaining problems.
Date: April 1964
Creator: DuBridge, R. A.
System: The UNT Digital Library
Ozone and Nitrogen Oxide Production by Irradiation of Air (open access)

Ozone and Nitrogen Oxide Production by Irradiation of Air

In regard to the production of ozone and various nitrogen oxides in air by action of x-rays or gamma rays, thre seems to be no direct experimental data which can be used. There is some data on the action of alpha particles on air and some on the action of cathode rays.
Date: December 21, 1950
Creator: Newton, A. S.
System: The UNT Digital Library
A Low Voltage Ion Source (open access)

A Low Voltage Ion Source

Describes the investigation of a particular method of extracting ions from an arc. Experimental results of a low extraction voltage ion source are given in some detail.
Date: July 12, 1951
Creator: Foster, J. S., (John Stuart), 1890-1964 & Martina, Eugene F.
System: The UNT Digital Library
Technical Activities Report for April 1953 (open access)

Technical Activities Report for April 1953

Two xenon extraction runs were made this month. It appears that a small design change in Trap #2 will be necessary so that a dry ice-trichloroethylene slurry can be used for coolant rather than liquid freon. For each of the runs this month the enriched generator was exposed for four hours in the est pile operating at 100 watts. A period of eight hours for cooling and xenon builidup was allowed before the collection and separation runs were started.
Date: May 4, 1953
Creator: Faulkner, J. E.; Davenport, D. E. & Duvall, G. E.
System: The UNT Digital Library
The Identification of the Angular Inclusions Present in Rolled Uranium (open access)

The Identification of the Angular Inclusions Present in Rolled Uranium

Hanford uranium contains minute angular inclusions which affect the microstructure, reactivity, and other important factors controlling the serviceability of the metal. Small quantities of the inclusions have been isolated by chemical means, and the x-ray diffraction patterns and chemical analyses of the isolated materials have been determined. As a first step in the identification of the inclusions present in rolled uranium, a search was made for a chemical method of separating the inclusions from the matrix metal.
Date: May 15, 1953
Creator: Scott, F. A.
System: The UNT Digital Library
Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3 (open access)

Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3

This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).
Date: June 14, 1960
Creator: Amos, L. C.; Kirkendall, B. E. & Adler, K. L.
System: The UNT Digital Library
Removal of Graphite from Aluminum Surfaces (open access)

Removal of Graphite from Aluminum Surfaces

The first of two general methods are discussed based on the removal of the thin layer of aluminum to which graphite adheres. Two electro-polishing techniques, an electrolytic etch, an anodization-deanodication cycle and two chemical etches are described.
Date: June 30, 1953
Creator: Dillon, R. L. & Hodgson, W. H.
System: The UNT Digital Library
The Spectrophotometric Determination of Boron in Plutonium Using an Oxalate Separation (open access)

The Spectrophotometric Determination of Boron in Plutonium Using an Oxalate Separation

An improved method for the determination of boron in plutonium is reported. Precipitation of plutonium (III) acid oxalate prior to color development with curcumin results in increased precision, greater speed, and lower costs. Results are presented of a statistical study involving all variables.
Date: June 25, 1953
Creator: Newell, Donald M.
System: The UNT Digital Library
Spectrographic Analysis of Plutonium by the Thenoyltrifloroacetone Extraction Method (open access)

Spectrographic Analysis of Plutonium by the Thenoyltrifloroacetone Extraction Method

Impurities are separated from plutonium solutions by means of TTA (thenoyltrifluoracetone) extractions. Plutonium in hydrochloric acid solution is reduced to the trivalent state with hydroxylamine, and some impurities are extracted into hezone or a solution of TTA in hezone. The organic phase is removed, and the plutonium in the aqueous phase is oxidized to the tetravalent state with nitric acid. Investigations of several variables which affect the extraction are described..
Date: June 29, 1953
Creator: Van Tuyl, H. H.
System: The UNT Digital Library
Monitoring Thermal and Resonance Neutron Flux (open access)

Monitoring Thermal and Resonance Neutron Flux

The monitoring of thermal and resonance neutron flux in a thermal reactor having high flux over periods of time from 1 to 12 months using think Co foils is considered. Special attention is paid to the many correction factors to be applied to the activation data; neutron temperature, effective cadmium cutoff energy, burnout of Co59 and Co60, and decay of Co60. Results on a homogeneity test of 10 mil, 0.08% Co-A1 alloy foils is given.
Date: August 17, 1953
Creator: Heineman, R. E.
System: The UNT Digital Library
Radiological Sciences Department:  Quarterly Progress Report, Research and Development Activities, July-September, 1953 (open access)

Radiological Sciences Department: Quarterly Progress Report, Research and Development Activities, July-September, 1953

This is the sixteenth quarterly report of the research and development activities of the Radiological Sciences Department, Hanford Atomic Products Operation, as before, includes some items charged to control but included for general interest. Such are identified as "not charged to research."
Date: October 2, 1953
Creator: Parker, H. M.
System: The UNT Digital Library
Interim Report of Nuclear Analysis Performed on SM-2 Core and Vessel : September 1, 1958 to December 31, 1959. (open access)

Interim Report of Nuclear Analysis Performed on SM-2 Core and Vessel : September 1, 1958 to December 31, 1959.

Abstract: This technical report contains a description of the nuclear analysis performed upon the SM-2 core and vessel for the period September 1, 1958 to December 31, 1959. Calculations are given for core reactivity, power distributions, lifetime, reactor control, kinetics, radiation problems, fuel and poison burn-ups, and the nuclear effects of poisons, temperature, and geometry. Wherever possible, experimental data is included in order to test the validity of the analytical models. The SM-2 nuclear analysis was performed by Alco Products, in. under Tasks 1, 8, and 10 of Contract No. AT(30-2)-326 for the Atomic Energy Commission.
Date: May 27, 1960
Creator: Bobe, P. E.; Birken, S. H.; Byrne, B. J.; Clancy, E. F. & Fried, B. E.
System: The UNT Digital Library
Analysis of Zero Power Experiments on SM-1 Core II and SM-1A Core I (open access)

Analysis of Zero Power Experiments on SM-1 Core II and SM-1A Core I

Abstract: An analysis of SM-1 Core II and SM-1A Core I zero power experiments was made by comparing these cores to each other and to AM-1 Core I on the basis of critical bank positions, bank calibrations and available chemical analyses of the fuel plate compositions. The effects of replacing boron absorbers by europium absorbers upon rod worth and stuck rod conditions were studied. Comparisons of measured and calculated power distributions were made. It was concluded that both SM-1 Core II and SM-1A Core I contain nearly identical B-10 loading of 17.79 grams, compared to the best estimate of 15.75 grams for SM-1 Core I. The available data indicates that all three cores possess similar nuclear characteristics.
Date: October 5, 1960
Creator: Paluszkiewicz, S.
System: The UNT Digital Library
Fission Product Activity in SM-1 Core I Primary System and Surface Contamination on SM-1 Type Fuel Elements. Task XVIII, Phases 2 and 3 (open access)

Fission Product Activity in SM-1 Core I Primary System and Surface Contamination on SM-1 Type Fuel Elements. Task XVIII, Phases 2 and 3

Abstract; The fission product data obtained during SM-1 Core I operation (June 1957 - May 1960) is reviewed briefly and interpreted. Evidence is presented to indicate that a fuel element defect was responsible for the high fission product activity level observed in the primary coolant. Relative escape coefficients are calculated and the defect size estimated. Anticipated fission product levels during SM-1 Core II and SM-1A Core I operation are estimated from alpha surface contamination data on completed fuel elements. The importance of in-line sampling for monitoring fission product activity is stressed as well as the need for failed fuel element detection methods.
Date: February 28, 1961
Creator: Hasse, Robert A. & Zegger, John L.
System: The UNT Digital Library
Hazards Report for SM-1 Core Temperature and Flow Instrumentation (Task XIV) Covering Special Test Procedures. (open access)

Hazards Report for SM-1 Core Temperature and Flow Instrumentation (Task XIV) Covering Special Test Procedures.

Abstract: Test procedures for special tests involving in-core SM-1 temperature and flow instrumentation are described (Task XIV Package Tests). These tests involve in-core steady state flow and temperature measurements, loss of flow transients, load transients, reduced primary system pressure operations and reduced element flow. The thermal and hydraulic conditions prevailing in these tests, including steady state and transient burnout rations, are developed. The effects of reduced system pressure and flow on the burnout ratios are determined as are the expected stuck rod conditions when Task XIV test elements are installed. The effect on the maximum credible accident is included and a recommendation to conduct these Task XIV package tests is made.
Date: February 28, 1962
Creator: Bradley, P. L. & Coombe, J. R.
System: The UNT Digital Library
Hazards Report for the SM-1 Core II With Special Components (open access)

Hazards Report for the SM-1 Core II With Special Components

Abstract: This technical report describes the changes incurred in the SM-1 by the insertion of the SM-1 Core II and special components. The special components consist of impact specimens, a boron gradient rod, SM-2 elements, a PM-1-M element, and high burnup SM-1 Core I elements. The change in hazards, due to operation of SM-1 with Core II and the special components is evaluated. The analysis indicates there is no change in hazards.
Date: March 30, 1961
Creator: Coombe, J.; Lee, D.; Segalman, I. & Robertson, R.
System: The UNT Digital Library