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Status Report on the Argonne Advanced Research Reactor
The interim design and development status is reported. The scope of the work was limited to conceptual design studies supported by critical experiments plus heat transfer and hydraulic tests. Design criteria, facility and site, reactor, core geometry and composition, fuel elements, reflector, core and reflector support structure, reactor vessel, control and instruments, primary coolant systems, secondary coolant system, auxiliary systems, experimental facilities, building layout and construction, plant ventilation, heating and air conditioning, critical experiments, reactor physics, heat transfer studies, and shieldings are discussed. (M.C.G.)
Date:
November 1, 1961
Creator:
Lennox, D. H.; Barts, E. W.; Batch, R. V.; Beyer, F. C.; Jorgensen, G. L.; Kelber, C. N. et al.
Object Type:
Report
System:
The UNT Digital Library
BRAZING OF CERAMICS. Progress Report
Brazing alloys such as 48 Ti-48 Zr-4 Be (wt%) and 49 Ti-49 Cu-2 Be (wt%) have been found to readily flow on oxide and graphite ceramics. Two demonstrati on fuel element assemblies were fabricated to illustrate the usefulness of these procedures for nuclear applications. One of these assemblies contained graphite tubes and end caps which were brazed to a molybdenum hanger. The second demonstration fuel element was composed of a compartmented aluminum oxide plate to which aluminum oxide cover plates were brazed. (R.J.S.)
Date:
November 1, 1962
Creator:
Fox, C.W.
Object Type:
Report
System:
The UNT Digital Library
Cost Function Studies for Power Reactors
A function to evaluate the cost of electricity produced by a nuclear power reactor was developed. The basic equation, revenue = capital charges + profit + operating expenses, was expanded in terms of various cost parameters to enable analysis of multiregion nuclear reactors with uranium and/or plutonium for fuel. A corresponding IBM 704 computer program, which will compute either the price of electricity or the value of plutonium, is presented in detail. (auth)
Date:
November 1, 1961
Creator:
Heestand, J. & Wos, L.T.
Object Type:
Report
System:
The UNT Digital Library
New Solutions of the Boltzmann Equation for Monoenergetic Neutron Transport in Spherical Geometry
Solutions of the Boltzmann equation for monoenergetic neutron transport in spherical geometry are derived which are respectively singular and regular at the center of the sphere. A few specific partial singular solutions are presented. The regular solutions in spherical geometry are constructed by superposition of solutions in plane geometry which belong to the same k. Finally, the solutions are compared with their representations by a series of spherical harmonics. (D. L.C.)
Date:
November 17, 1961
Creator:
Kofink, W.
Object Type:
Report
System:
The UNT Digital Library
Mass Transfer Coefficients and Interfacial Area in a One Stage Pulse Column
Over-all mass transfer coefficients were determined independently of the interfacial area by considering the operation of the pulse column to be a stage- wise process. The calculated coefficients describe only the operation of the pulse column for the free rise of organic droplets through a stage, since in the downstroke the aqueous phase passes through the organic phase in the form of rivulets preferentially wetting the plates. The driving force for transfer was based on the aqueous phase concentrations. The mass transfer coefficient was found to increase when the interfacial tension was reduced. Two factors appear to affect the mass transfer coefficient as the pulse frequency is changed and are: a) recycle or backmixing which tends to decrease the coefficient through a reduction of acetic acid in both phases and thereby increases the interfacial tension, and b) turbulence which enhances the coefficient by reducing the continuous film resistance. The first is important at or near the lower flooding limit, but the latter is the controlling factor at higher frequencies. (D.L.C.)
Date:
November 1, 1960
Creator:
Konopik, A. E. & Burkhart, L.
Object Type:
Report
System:
The UNT Digital Library
PROCESSES FOR RECOVERY OF URANIUM AND THORIUM FROM GRAPHITE-BASE FUEL ELEMENTS. PART II
Laboratory-scale tests on methods for recovering uranium and thorium from graphite-base reactor fuel elements are reported. The 90% HNO/sub 3/ process, which involves simultaneous disintegration and leaching in 21 M HNO/sub 3/, is applicable to all fuel elenments which do not contain coated fuel particles. Leaching of irradiated (0.001% burnup) fuels containing 3 and 12% uranlum recovered approximates 99.3 and 99.9%, respectively, of the uranium in two 4-hr leaches with boiling acid. The graphite residue retained > 50% of the long-lived fission products. Three successive leaches of fuel containing uranium and thorium recovered approximates 99% of both elements. Uranium recoveries by combustion in oxygen followed by dissolution of the ash hn nitric acid or fluorlde-catalyzed nitric acid are quantitative only when the fuel is not coated, does not contain Al/sub 2/O/sub 3/-coated fuel particles, and is free from impurities such as iron. During combustion up to 95% of the Ru-106 was volatilized from irradiated specimens. Recoveries, by leaching with 70% HNO/sub 3/, from fuel specimens containing Al/sub 2/O/sub 3/-coated fuel particles were greater than 99% when the specimens were ground finer than 200 mesh to ensure crushing of the fuel particles. (auth)
Date:
November 30, 1961
Creator:
Ferris, L.M.; Kibbey, A.H. & Bradley, M.J.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Wire Scanner for SM-1
Preliminary design concepts are presented for a wire scanner for experimentally evaluating spatial variations of neutron flux in the SM-l reactor core. Results of a literature search and determination of optimum criteria for flux mapping the core in minimum time dictated requirements for design concepts and specifications. The utility of both manually instrumented and automatically instrumented wire scanners was analyzed with respect to rapidity of measurement, selectivity of detector location, cost, value of data, plant downtime, and additional factors. (auth)
Date:
November 22, 1961
Creator:
Kemp, S. N.
Object Type:
Report
System:
The UNT Digital Library
CONCEPTUAL DESIGN AND ECONOMIC EVALUATION OF A STEAM-COOLED FAST BREEDER REACTOR
A conceptual design and economic evaluation of 300 and 40 MW/.sub e/ steam-cooled fast breeder reactor power plants were performed. A reactor core composed of U-Pu oxide rod-type fuel elements clad with Inconel-X and surrounded by a blanket of depleted UO/sub 2/ fuel was studied in some detail. Reactor breeding ratios of from 1.27 to 1.5 and overall system doubling times of from 20 to 30 years are achievable. For the near term (1967) 300 MW/sub e/ plant, an energy cost of 7.6 mills/kwh is estimated, based on AEC ground rules for privately financed plants and utilities. This cost may go down to 5.7 mills/kwh by 1975. For the 40 MW/sub e/ plant corresponding energy costs are 19.5 and 13.7 mills/kwh, r -spectively. The R&D program required for this reactor concept is estimated at million with an additional million for improvements leading to the 1975 reactor. Investigation of the operational and safety aspects of the reactor indicated that satisfactory procedures can be used for startup, shutdown, and emergency cooling of the reactor. An increase in reactivity upon flooding can be prevented by incorprating small amounts of high resonance absorption material in the core. Preliminary calculations indicate a substantial increase in …
Date:
November 15, 1961
Creator:
Sofer, G.; Hankel, R.; Goldstein, L. & Birman, G.
Object Type:
Report
System:
The UNT Digital Library
CASTING OF LONG AND THIN PLATES OF URANIUM-MOLYBDENUM ALLOYS
The development of procedures for the vacuum induction casting of U--Mo alloys into both thin (0.010 to 0.100-in. thick) plates and long (36 in.) plates is described. Melting and casting cycles were developed, and casting techniques established, which resulted in sound, integral plates. These plates were evaluated by radiographic and metallographic examination, and by chemical analysis. The results indicated the feasibility of the process for the fabrication of fuel plates for nuclear reactors. The process promises a potential reduction in fabrication costs, by eliminating waste. (auth)
Date:
November 1, 1961
Creator:
Katz, N.H. & Binstock, M.H.
Object Type:
Report
System:
The UNT Digital Library
STUDIES OF THE SCINTILLATION PROCESS IN CsI(Tl)
The scintillation response of CsI(Tl) crystals, having various thallium contents, was measured for excitation of the crystals by monoenergetic gamma rays, protons, and alpha particles. The investi gation was made to provide a test of some of the features of a theoretical model of the scintillation process in thallium-activated alkali iodides proposed by Murray and Meyer. In order to insure that the results obtained in this program would provide a critical test of the scintillation model, special attention was paid to technical effects which could influence the interpretation of the experimental data. For example, the effect of the pulseanalysis time on the relative scintillation response of CsI(Tl) to various charged parti cles was investigated. In addition, the emission spectra of the CsI(Tl) crystals were measured for excitation by x rays, protons, and alpha particles. The results of the investigation showed that the scintillation efficiency of CsI(Tl) is a continuous function of dE/dx, as assumed in the scintillation model, within the accuracy of the experiments when the effect of delta ravs are considered. This led to the conclusion that the light output of CsI(Tl) crystals is, in general, a nonlinear function of the energy of the particle. The shape of the …
Date:
November 30, 1962
Creator:
Gwin, R. & Murray, R. B.
Object Type:
Report
System:
The UNT Digital Library
The Thermodynamic Properties of the Alkali Halides
The thermodynamic properties of the alkali halides are reviewed, presenting data supplementary to that of Brewer and Brackett, Chem. Rev. 61: 425-432(1961). (T.R.H.)
Date:
November 1961
Creator:
Brewer, L.
Object Type:
Report
System:
The UNT Digital Library
A High-Temperature, Fluidized-Bed Process for Converting Uranium Dioxide to Uranium Monocarbide.
None
Date:
November 1968
Creator:
Holmes, John T.; Pavlik, John R.; Nelson, Paul A. & Graae, Johan E. A.
Object Type:
Report
System:
The UNT Digital Library
The Federal Flag Code Including Selected Questions and Answers
This report includes text of the Act, and of the Presidential Proclamation relating to the display of the flag at half-staff.
Date:
November 27, 1968
Creator:
Hutton, E. Jeremy
Object Type:
Report
System:
The UNT Digital Library
Pakistan: A Bibliography
This report is a bibliography that cites information related to Pakistan. It includes General, History, Government and Politics, Economy and Development, Foreign policy, and defense.
Date:
November 25, 1969
Creator:
Patitucci, Jean B.
Object Type:
Report
System:
The UNT Digital Library
Congressional Delegation of Administrative Discretion to the Executive Branch: The Separation of Powers
This report was written in response to the Congressional action of delegating the power of implementing regulations that have the force and effect of law to members of the Executive branch such as federal agencies. The report collects and evaluates material pertinent to a wide range of questions in the area of the legislative practice of imposing criminal sanctions for violations of the administrative regulations which are a product of legislation.
Date:
November 1, 1968
Creator:
American Law Division
Object Type:
Report
System:
The UNT Digital Library
The New Left: Students for a Democratic Society, A Supplement
This report discusses Students for a Democratic Society (SDS) and their Marxist views and activities aimed at uniting students and workers. Splinter factions of SDS which staged violent protests in Chicago in the summer of 1969 are discussed in detail along with a prognosis on their likely levels of success in recruiting more students to their cause.
Date:
November 26, 1969
Creator:
Jones, Richard S.
Object Type:
Report
System:
The UNT Digital Library
The Seniority System in Congress: A Selected Bibliography
This report provides a bibliography of resources related to the seniority system in Congress.
Date:
November 12, 1969
Creator:
Kravitiz, Walter
Object Type:
Report
System:
The UNT Digital Library
[News Script: County]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
November 13, 1968
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library
[News Script: Hopstadter]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
November 7, 1968
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library
[News Script: Wreck]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
November 19, 1968
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library
[News Script: Shoplifters]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
November 20, 1968
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library
[News Script: Shooting]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
November 13, 1968
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library
[News Script: Fort Worth council]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
November 25, 1968
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library
[News Script: Mary Martin]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
November 24, 1968
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library