A Bench-Scale Natural-Recirculation Dissolver (open access)

A Bench-Scale Natural-Recirculation Dissolver

A natural-recirculation dissolver closely approaching a stirred-tank reactor in behavior was developed, and its feasibility was demonstrated in the mercury-catalyzed dissolution of aluminum in nitric acid, It was designed to utilize the heat of reaction and evolution of gaseous reaction products for recirculation and mixing. The dissolvent was 5-molar nitric acid, containing mercury in concentrations from 10/sup -4/ to 10/sup -3/ molar as a catalyst. Dissolution rates for 1/7 scale, simulated MTR fuel elements of 2-S aluminum ranged from 0.25 to 4.0 mg/(cm/sup 2/)(rain), depending on the catalyst concentration in the dissolvent and the dissolvent flow rate. For comparable catalyst and acid feed concentrations, dissolution rates, based on unit net superficial velocities, were nearly 25 times those for dissolution of randomly- packed flat plates in a pilot plant, continuous, flooded dissolver. (auth)
Date: January 10, 1962
Creator: Erickson, E. E.
Object Type: Report
System: The UNT Digital Library
Critical Path Scheduling of ETR and MTR Reactor Shutdowns (open access)

Critical Path Scheduling of ETR and MTR Reactor Shutdowns

Report describing a method for planning shutdown projects and scheduling the manpower to shut down Materials Testing Reactors (MTR) and Engineering Test Reactors (ETR).
Date: January 10, 1962
Creator: Jacobs, R. T. & Myers, L. L.
Object Type: Report
System: The UNT Digital Library
INDUSTRIAL CRITICALITY MEASUREMENTS ON ENRICHED URANIUM AND PLUTONIUM. PART II (open access)

INDUSTRIAL CRITICALITY MEASUREMENTS ON ENRICHED URANIUM AND PLUTONIUM. PART II

ABS>A series of neutron multiplication measurements made on sub-critical systems containing enriched uranium and plutonium is presented. These measurements involve both aqueous and metal systems. (auth)
Date: January 10, 1962
Creator: Schuske, C.L.; Bell, C.L.; Bidinger, G.H. & Smith, D.F.
Object Type: Report
System: The UNT Digital Library
Literature Survey on World Isotope and Radiation Technology : First Semi-Annual Report Covering the Period from June 15, 1961 to December 14, 1961 (open access)

Literature Survey on World Isotope and Radiation Technology : First Semi-Annual Report Covering the Period from June 15, 1961 to December 14, 1961

The following report is the first semi-annual report of a literature survey designed to investigate the uses and technology of radioisotopes in the countries of the world from 1955 to the present. This survey includes two phases: 1) involves the direct comparison of radioisotopic work in all fields in various countries as demonstrated at international conferences. 2) involves a more detailed examination and evaluation of the individual fields of interest selected previously (Phase II is also expected to comprise the bulk of the remainder of this investigation).
Date: January 10, 1962
Creator: Haffner, J. W. & Terrell, C. W.
Object Type: Report
System: The UNT Digital Library
Numerical Analysis of Neutron Resonances (open access)

Numerical Analysis of Neutron Resonances

Neutron resonances are analyzed numerically by determining the resonant energies, the total widths, and the neutron widths of the resonances. It was assumed that the total cross section can be represented by the sum of single- level Breit-Wigner formulas, with interference between resonance and potential scattering but no interference between resonances; that the Doppler broadening is represented by a Gaussian function; and that the instrument resolution is represented by a Gaussian function. Gauss' method was used to reduce the nonlinear problem to one in which linear methods can be applied. Some unusual techniques were used for evaluating the integrals in the function for calculating the transmission. Two programs for analyzing transmission data to obtain the parameters of the resonances were written for the IBM 7090 computer. The first program is a shape analysis for determining the resonant energies, the total widths, and the neutron widths of the resonances. This program analyzes the transmission data for as many as six resonances at once. The second program is an area analysis for determining the neutron widths of the resonances for assumed total widths. This program analyzes transmission data containing as many as 20 resonances at once. (auth)
Date: January 10, 1962
Creator: Atta, S.E. & Harvey, J.A.
Object Type: Report
System: The UNT Digital Library
Supporting Analysis for Thermal Suitability of Fuel Elements for SM-1A Core I Loading (open access)

Supporting Analysis for Thermal Suitability of Fuel Elements for SM-1A Core I Loading

A recommended SM-1A Core I loading chart was derived from available, metallurgically acceptable elements at the SM-1A and SM-1 sites. The derivation was based on local thermal and hydraulic considerations of minimum elementto- element coolant channel clearances. These clearances were determined from field inspection measurements of outer fuel plate spacing, as modified by analytical calculations of plate ripple growth during exposure to reactor operating thermal stresses. (auth)
Date: January 10, 1962
Creator: Brondel, J. O.
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: WW-1238 (open access)

Texas Attorney General Opinion: WW-1238

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Waiver of salary of District Clerk when called into the Military Service.
Date: January 10, 1962
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
SNAP Program Milestones (Addendum-9) (open access)

SNAP Program Milestones (Addendum-9)

None
Date: March 10, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
The Structures of NiZr$sub 2$, NiZr and Their Hafnium Analogs (open access)

The Structures of NiZr$sub 2$, NiZr and Their Hafnium Analogs

None
Date: March 10, 1962
Creator: Kikpatrick, M. E.; Bailey, D. M. & Smith, J. F.
Object Type: Article
System: The UNT Digital Library
Chemical Technology Division Unit Operations Section Monthly Progress Report, December 1961 (open access)

Chemical Technology Division Unit Operations Section Monthly Progress Report, December 1961

The height of transfer units in a 6-in.-ID foam-liquid column for isotopic exchange or stripping of Sr using Sr/sup 89/ tracer were 1.4 to 4.6 in. Denitration of Th(NO/sub 3/)/sub 4/ in an agitated trough to give thoria for dispersion into a sol is reproducible. The loading of UF/sub 6/ on a single layer of 1/8in. right circular cylinders of NaF in the presence of a flowing UF/ sub 6/-N/sub 2/ stream showed strong dependence on gas concentration in the range of 0.58 to 8.0 mole% UF/sub 6/ and a weaker dependence on temperature in the range from 25 to 100 deg C. Eleven tests were made using simulated Darex, TBP-25, and TBP-25 with organic waste demonstrating the batch and continuous flowsheets with good stable control of the continuous evaporator. (auth)
Date: April 10, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Object Type: Report
System: The UNT Digital Library
Corrosion of thorium and uranium during long-term storage (open access)

Corrosion of thorium and uranium during long-term storage

From introduction: "The over-all objective of the present study was to determine the nature and extent of the present study was to determine the nature and extent of the corrosion of these materials under a variety of such storage conditions and to determine the ability of several potential protective coatings to retard this corrosion."
Date: April 10, 1962
Creator: Stephan, Elmer F.; Miller, P. D. & Fink, Frederick W.
Object Type: Report
System: The UNT Digital Library
Effect of Exposure Site on Weather Resistance of Porcelain Enamels Exposed for Three Years (open access)

Effect of Exposure Site on Weather Resistance of Porcelain Enamels Exposed for Three Years

From Introduction: "The present report describes the condition of all of the porcelain enamels after exposure for 3 yr."
Date: April 10, 1962
Creator: Moore, Dwight G. & Potter, Alan
Object Type: Report
System: The UNT Digital Library
Equations for Bilateral Heat Transfer to Fluids Flowing in Concentric Annuli (open access)

Equations for Bilateral Heat Transfer to Fluids Flowing in Concentric Annuli

Abstract: "Theoretical equations have been derived for calculating heat transfer coefficients for fluids flowing through concentric annuli for the following two cases: (A) constant and equal heat fluxes from both walls, and (B) constant, but unequal, heat fluxes from the walls, with equal wall temperatures at a given axial position along annular channel. In the derivations, the conditions of fully-established flow, and independence of physical properties with temperature variation across the flow channel, were assumed. The only geometrical parameter in this general case is the radius ratio r2/r1, and in the study it was varied from 1.0 to 10.0."
Date: April 10, 1962
Creator: Dwyer, Orrington Embry, 1912-
Object Type: Report
System: The UNT Digital Library
NEUTRON THERMALIZATION MEASUREMENTS USING AN ELECTRON LINEAR ACCELERATOR (open access)

NEUTRON THERMALIZATION MEASUREMENTS USING AN ELECTRON LINEAR ACCELERATOR

Discussions are presented concerning integral experiments primarily on water and graphite systems. A description of experimental facilities is included along with details of die-away experiments, infinite-medium spectrum measurements, spatially dependent spectrum measurements, spectrum measurements for graphite systems, and development of a subcritical assembly program. (J.R.D.)
Date: April 10, 1962
Creator: Beyster, J R
Object Type: Report
System: The UNT Digital Library
PL-3 Project Quarterly Progress Report, January 1, 1962-March 31, 1962 (open access)

PL-3 Project Quarterly Progress Report, January 1, 1962-March 31, 1962

Progress is reported on phase II in sections on final design, procurement, fabrication, testing, packaging, and crew training. A summary of completed phase I work on concept evaluation and preliminary design is also included. (J.R.D.)
Date: April 10, 1962
Creator: Humphries, G. E.
Object Type: Report
System: The UNT Digital Library
The power output and efficiency of thermionic converters connected in series and parallel circuits--Part I (open access)

The power output and efficiency of thermionic converters connected in series and parallel circuits--Part I

Optimum and off-optimum performance is experimentally obtained for one of the 10 mil spaced, 7 cm/sup 2/ emitter area, cylindrical geometry thermionic converters to be used in the series and parallel connected thermionic converter experiment. The results are presented as graphs of output voltage vs power input, and power output vs power input. The current is the major parameter in both cases. The data in these forms are used to compute the power output of twin converter circults having unequal power inputs. The optimum load conditions for operation are then determined. The results are valuable in guiding thermionic power plant design. (auth)
Date: April 10, 1962
Creator: Holland, J. W.
Object Type: Report
System: The UNT Digital Library
Removal of radioisotopes from the Columbia River by natural processes (open access)

Removal of radioisotopes from the Columbia River by natural processes

Some radioisotopes are introduced into the Columbia River by return of the water used to cool the Hanford reactors. Trace amounts of both fission product and activation product radioisotopes are present and measurable by sensitive radiochemical methods to allow determination of the self-purification processes occurring as the water moves downstream. By comparing the radioisotope input at given times with the amounts present in the river after traveling downstream, a measure of the self-purification rate was obtained. Removal in the first 40 miles downstream from the reactors was about 35% for 15 of the most prominent radioisotopes. The removal rate seemed to decrease with subsequent distance traveled downstream for three radioisotopes for which measurements were made. Radiochemical analyses of water, filterable solids, and sediment samples taken at downstream locations indicate that incorporation in sediments accounts for most of the removal. Because of the intense scouring action of the Columbia River, sediments are deposited in significant amounts only in slack water sections. The first extensive slack water section downstream from Hanford is the McNary Dam reservoir, Lake Wallula. Radiochemical analyses of some of the long-lived radioisotopes, including Mn/sup 54/, Co/sup 60/, Zn/sup 65/, and Cs/sup 147/ on sectioned sediment core samples indicate …
Date: April 10, 1962
Creator: Nielsen, J. M. & Perkins, R. W.
Object Type: Report
System: The UNT Digital Library
SNAP Program Milestones (Addendum - 10) (open access)

SNAP Program Milestones (Addendum - 10)

flight hardware delivery dates; milestone charts
Date: April 10, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: WW-1304 (open access)

Texas Attorney General Opinion: WW-1304

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether witness fees may be paid to witnesses who reside in the county where a felony is tried.
Date: April 10, 1962
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Cation Exchange in Acetone-Water-Hydrochloric Acid (open access)

Cation Exchange in Acetone-Water-Hydrochloric Acid

Abstract: Distribution coefficients have been measured for the partition of metal ions between cation exchange resin and acetone-water-hydrochloric acid solutions. the differences in distribution coefficients of metal ions are greater in acetone-water media than in aqueous media of the same hydrochloric acid concentration. Using distribution coefficient data, conditions for column separations of mixtures can be selected. Column separations of metal ion mixtures can be effected by eluting with acetone-water-hydrochloric acid solutions of different compositions. Successful separations of a number of mixtures are reported.
Date: May 10, 1962
Creator: Fritz, James S. (James Sherwood), 1924- & Rettig, Thomas A.
Object Type: Report
System: The UNT Digital Library
FPD facilities - radiological status (open access)

FPD facilities - radiological status

None
Date: May 10, 1962
Creator: Black, B. R.
Object Type: Report
System: The UNT Digital Library
Fuel Element Flow Blockage in the Engineering Test Reactor (open access)

Fuel Element Flow Blockage in the Engineering Test Reactor

On December 12, 196l, the Engineering Test Reactor experienced fuel fission breaks which resulted from obstructions to the flow of cooling water through several fuel elements. A total of six fuel elements had breaks in from one to eight fuel plates. A discussion and description of damage to the fuel is presented. The reactor operating conditions preceding the break are described, including events immediately before the manual scram. Results of investigations conducted after the scram, including effects upon the reactor as well as fuel element damage, are reported. (auth)
Date: May 10, 1962
Creator: Keller, F. R.
Object Type: Report
System: The UNT Digital Library
INVESTIGATION OF THERMALSTRESS-FATIGUE BEHAVIOR OF STAINLESS STEEL. THE EFFECTS OF GAGE LENGTH AND SPECIMEN CONFIGURATION ON THERMAL-STRESS-FATIGUE TEST RESULTS (open access)

INVESTIGATION OF THERMALSTRESS-FATIGUE BEHAVIOR OF STAINLESS STEEL. THE EFFECTS OF GAGE LENGTH AND SPECIMEN CONFIGURATION ON THERMAL-STRESS-FATIGUE TEST RESULTS

The importance of the experimental method to thermalstress-fatigue test results is clarified. It is shown that a significant increase in apparent fatigue life can be obtained by measuring maximum strain per cycle instead of an average strain. Extrapoiation curves are given to convert the litter into the formed. A varying-cross-section specimen of zero'' gage length is shown to allow measurement of true, maximum strain. (auth)
Date: May 10, 1962
Creator: Horton, K. E.
Object Type: Report
System: The UNT Digital Library
PL FINAL DESIGN REPORT. VOLUME VI. PLANT PERFORMANCE ANALYSIS (open access)

PL FINAL DESIGN REPORT. VOLUME VI. PLANT PERFORMANCE ANALYSIS

Data and information are presented concerning analyses of PL-2 transient performance, normal startup and shutdown procedures, and shield design. (J.R.D.)
Date: May 10, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library