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Correlation of mechanical and metallurgical parameters with the acoustic emission during tensile deformation of several metals and alloys (open access)

Correlation of mechanical and metallurgical parameters with the acoustic emission during tensile deformation of several metals and alloys

Acoustic emission was monitored during plastic deformation under dead-weight tensile loading of polycrystalline aluminum, brass, copper, and steel. The acoustic emission data, both threshold-type and frequency-analysis type, were correlated with yield strength, stored elastic energy, strain hardening parameters, loading histories, diffusion processes, slip band motion and mosaic cell size. Major results are presented under the headings discontinuous yielding (Portevin--Le Chatelier Effect), parabolic strain hardening, and frequency analysis. The principal experimental techniques are also summarized. (auth)
Date: December 1, 1975
Creator: Hartman, W. F.
Object Type: Report
System: The UNT Digital Library
Review of fission product plateout investigations at General Atomic. [HTGR] (open access)

Review of fission product plateout investigations at General Atomic. [HTGR]

The status of fission product plateout studies at General Atomic is reviewed and suggestions are offered for future work. The deposition, or plateout, of condensible radionuclides in the primary circuits of gas-cooled reactors affects shielding requirements, maintenance procedures, and plant availability as well as representing a significant radiological source and/or sink for certain hypothetical accidents. Physical models and computer codes used to describe these plateout phenomena for reactor analysis are presented along with their limitations and possible refinements. The review includes portions of the recent AIPA study which sought to quantify the effects of uncertainties in input parameters on plateout code predictions. Major emphasis is placed upon the design methods verification program to assess the validity of plateout predictions by comparison of calculated behavior with experimental transport data.
Date: December 1, 1977
Creator: Hanson, D. L.
Object Type: Report
System: The UNT Digital Library
Lectures notes for introduction to environmental law (open access)

Lectures notes for introduction to environmental law

This four-hour overview course is designed to briefly describe the environmental law system. The course provides an overview that managers and technical people will find useful as a beginning course or a course that puts formerly taken detailed courses in perspective. The course begins by defining environmental law and describing the legal system that establishes compliance obligations. Then, all the major Environmental Acts such as The Water Pollution Control Act, The National Environmental Policy Act, Resource Conservation and Recovery Act (RCRA), and Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) are briefly described and interrelated. All the environmental DOE Orders, selected books, and other source material are referenced. Radioactive pollutants are not discussed; however, reference material is provided.
Date: December 1, 1991
Creator: Cadwell, J.J.
Object Type: Report
System: The UNT Digital Library
Strangeonia and kin; new results from kaon hadroproduction with LASS (open access)

Strangeonia and kin; new results from kaon hadroproduction with LASS

Recent results from a high statistics study of strangeonium mesons produced in LASS by an 11 GeV/c K{sup -} beam are reviewed and compared with the quark model. New data from a variety of final states (K*{ovr K*}, {phi}{phi}, {phi}{pi}{sup 0}) produced by hypercharge exchange are described, and compared with results from other hadroproduction modes and from J/{psi} decay. 17 refs., 12 figs.
Date: December 1, 1989
Creator: Aston, D.; Bienz, T.; Bird, F.; Dunwoodie, W.; Johnson, W.B.; Kunz, P. et al.
Object Type: Article
System: The UNT Digital Library
Development of BEACON technology. Quarterly report, January-March 1982 (open access)

Development of BEACON technology. Quarterly report, January-March 1982

The BEACON process involves the catalytic deposition of a highly reactive form of carbon from a gas stream which contains carbon monoxide. The carbon-depleted gas is combusted with air to produce power, and the carbon is reacted with steam to produce methane or hydrogen. Process conditions favoring the production of hydrogen were explored this quarter. Excess steam was found to suppress methane formation, and reduction of catalyst methanation activity was demonstrated. The effect of carbon loading on the physical stability of catalyst C77-K2 and the effect of trace sulfur levels on the chemical stability of the catalyst were examined. The carbon loading tests did not show the catalyst breakup that was expected. Tests of chemical stability of the catalyst in the presence of sulfur-containing gases showed a decline in performance even at levels as low as 4 ppM. Experiments conducted using a Paraho-type oil shale retort offgas as a feedstock showed that acceptable performance could be obtained by removing carbon dioxide from the feedgas. Design of the tandem two reactor system is continuing, along with cold flow testing of the proposed solids transfer system. A simplified thermodynamic analysis of the BEACON process shows that BEACON's increased efficiency over competing processes …
Date: December 1, 1982
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Design of the core support and restraint structures for FFTF and CRBRP (open access)

Design of the core support and restraint structures for FFTF and CRBRP

This paper presents and compares the design and fabrication of the FFTF and CRBRP reactor structures which support and restrain the reactor core assemblies. The fabrication of the core support structure (CSS) for the FFTF reactor was completed October 1972 and this paper discusses how the fabrication problems encountered with the FFTF were avoided in the subsequent design of the CRBR CSS. The radial core restraint structure of the FFTF was designed and fabricated such that an active system could replace the present passive system which is segmented and relies on the CSS core barrel for total structure integrity to maintain core geometry. The CRBR core restraint structure is designed for passive restraint only, and this paper discusses how the combined strengths of the restraint structure former rings and the CSS core barrel are utilized to maintain core geometry. Whereas the CSS for the FFTF interfaces directly with the reactor core assemblies, the CRBR CSS does not. A comparison is made on how intermediate structures in CRBR (inlet modules) provide the necessary design interfaces for supporting and providing flow distribution to the reactor core assemblies. A discussion is given on how the CRBR CSS satisfied the design requirements of the …
Date: December 1, 1977
Creator: Sutton, H.G. & Rylatt, J.A.
Object Type: Article
System: The UNT Digital Library
REACTIONS OF SELECTED HALOGENS AND INTERHALOGENS ACTIVATED BY RADIATIVE NEUTRON CAPTURE AND ISOMERIC TRANSITION WITH CONDENSED STATE CYCLOPENTANE AND AROMATIC HYDROCARBONS (open access)
Relation of air pollution to mortality: a critique. [SO/sub 2/ in New York City air] (open access)

Relation of air pollution to mortality: a critique. [SO/sub 2/ in New York City air]

A study of the relation between SO/sub 2/ and smoke-shade in the surface air of New York City and deaths resulting from respiratory and heart diseases is discussed. The need to use data from a number of sampling stations in any epidemiological study on the health effects of air pollutants is stressed. It is pointed out that the complicated effects of weather on the environmental transport of air pollutants and the variations in statistical methods used may lead to eronious conclusions as to the cause of deaths.
Date: December 1, 1977
Creator: Goldstein, I F; Goldstein, M & Landovitz, L
Object Type: Report
System: The UNT Digital Library
Centralized processing of contact-handled TRU waste feasibility analysis (open access)

Centralized processing of contact-handled TRU waste feasibility analysis

This report presents work for the feasibility study of central processing of contact-handled TRU waste. Discussion of scenarios, transportation options, summary of cost estimates, and institutional issues are a few of the subjects discussed. (JDL)
Date: December 1, 1986
Creator: unknown
Object Type: Report
System: The UNT Digital Library
REACTOR FUEL WASTE DISPOSAL PROJECT-PERMEABILITY OF ROCK SALT AND CREEP OF UNDERGROUND SALT CAVITIES. Final Report (open access)

REACTOR FUEL WASTE DISPOSAL PROJECT-PERMEABILITY OF ROCK SALT AND CREEP OF UNDERGROUND SALT CAVITIES. Final Report

A study was made of two problems of salt-cavity storage, namely, seepage of wastes out of formations and closure of cavities due to plastic flow of salt. The results indicate that both problems are negligible; bedded salt is more impermeable than dome salt. Kerosene was found to be nonreactive with dome salt whereas brine solutions showed some interaction. It is concluded that storage of radioactive wastes in salt cavities is feasible. (D.L.C.)
Date: December 30, 1960
Creator: Reynolds, T.D. & Gloyna, E.F.
Object Type: Report
System: The UNT Digital Library
Understanding radioactive waste (open access)

Understanding radioactive waste

This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes). (ATT)
Date: December 1, 1981
Creator: Murray, R.L.
Object Type: Report
System: The UNT Digital Library
CP violation (open access)

CP violation

Predictions for CP violation in the three generation Standard Model are reviewed based on what is known about the Cabibbo-Kobayashi-Maskawa matrix. Application to the K and B meson systems are emphasized. 43 refs., 13 figs.
Date: December 1, 1989
Creator: Gilman, Frederick J.
Object Type: Article
System: The UNT Digital Library
Annual highlights of programs in energy science. [Chemistry; materials; process] (open access)

Annual highlights of programs in energy science. [Chemistry; materials; process]

Progress is reported by the divisions of chemical sciences, metallurgy and materials science, and process sciences. a separate abstract was prepared for each division. (DLC)
Date: December 1, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Quarterly Status Report on the Advanced Plutonium Fuels Program, October 1-- December 31, 1967 (open access)

Quarterly Status Report on the Advanced Plutonium Fuels Program, October 1-- December 31, 1967

None
Date: December 31, 1968
Creator: unknown
Object Type: Report
System: The UNT Digital Library
GETTING MULTICHANNEL ANALYZER DATA IN AND OUT OF THE IBM-7090 FOR PROCESSING (open access)

GETTING MULTICHANNEL ANALYZER DATA IN AND OUT OF THE IBM-7090 FOR PROCESSING

The present method used for handling multichannelanalyzer data at the ORNL 86-Inch Cyclotron is stated. FORTRAN subroutines for reading the analyzer data into the IBM-7090 computer and for printing out the processed data and punching processed data on cards are presented. (auth)
Date: December 12, 1961
Creator: Goodman, C. D.
Object Type: Report
System: The UNT Digital Library
Phase Transformations in Alumina. Technical Report, May to December 1961 (open access)

Phase Transformations in Alumina. Technical Report, May to December 1961

e transformation studies showed that synthetic aluminas produced in the laboratory were not transformed to alpha alumina at 400 to 700' deg n the presence of nitric acid and water vapor. Amorphous aluminn produced in the pilot plant was transformed to alpha alumina. This indicated that the amorphous alumina produced in the pilot plant is structurally predisposed to form alpha alumina. Most additives did not appear to have any special effects. Lithium formed zeta alumina, LiAl/sub 5/O/sub 8/. Phosphate formed an unidentified phase. Zinc formed zinc aluminate. Sulfate favored higher water and lower nitrate contents than any of the other additives and formed natroalunite in one sample. The synthetic aluminas were heated in the micro reactor at pressures of 150 to 1300 psi. Most of the synthetic aluminas containing sodium formed alpha alumina while those without sodium did not, which agreed with the pilot plant results. Additives which allowed alpha alumina to form were calcium, iron, and lithium. Potassium, silicate, sulfate and zinc allowed alpha alumina to form when sodium was also present. Phosphate, boric acid, and magnesium seemed to prevent the formation of alpha alumina. Fission products, at 10 times the expected amount, also appeared to prevent formation of …
Date: December 1, 1961
Creator: Eding, H J; Huggins, M L & Brown, A G
Object Type: Report
System: The UNT Digital Library
High performance, suppressed-fission ICF hybrid (open access)

High performance, suppressed-fission ICF hybrid

The neutronics aspects of an ICF hybrid concept are discussed. The breeding blanket consists of a beryllium neutron multiplier, metallic thorium fertile fuel and a liquid-lithium coolant. The fertile fuel fraction is 30 vol%, which is much higher than previous one-zone, suppressed-fission hybrid concepts. Fission in the bred /sup 233/U is suppressed by competition from tritium breeding reactions in /sup 6/Li. The total breeding ratio, T + F, is 2.05, and the total neutron energy deposited is 41.1 MeV per DT neutron. The 800-MW (fusion) hybrid produces approx. 3500 kg of /sup 233/U per full-power-year.
Date: December 1, 1983
Creator: Meier, W. R.
Object Type: Article
System: The UNT Digital Library
Assessment of the response of spent fuel transports to malevolent acts (open access)

Assessment of the response of spent fuel transports to malevolent acts

This paper describes the results of a program conducted at Sandia National Laboratories (SNL) for the US Department of Energy to provide an experimental data base for more accurately assessing the radiological consequences from a hypothetical sabotage attack on a spent fuel shipping cask. The primary objectives of the program were limited to: (1) evaluating the effectiveness of selected high explosive devices (HED) in breaching full-size spent fuel casks, (2) quantifying and characterizing relevant aerosol properties of the released fuel, and (3) using the resulting experimental data to evaluate the radiological health consequences resulting from a hypothetical sabotage attack on a spent fuel shipping cask in a densely populated area. Subscale and full-scale experiments in conjunction with an analytical modeling study were performed to meet the programmatic objectives. The data from this program indicate that the Urban Studies greatly overestimated the impact of malevolent acts directed at spent fuel casks in urban environs. From that standpoint this work could be the basis of additional regulatory revisions of the NRC physical protection requirements. In a larger sense this work can also be the basis of more credible worst case analyses since it defines the actual result of an event which is …
Date: December 20, 1983
Creator: Sandoval, R.P.
Object Type: Article
System: The UNT Digital Library
Proceedings of the conference on research for the development of geothermal energy resources held in Pasadena, California, September 23--25, 1974 (open access)

Proceedings of the conference on research for the development of geothermal energy resources held in Pasadena, California, September 23--25, 1974

None
Date: December 31, 1974
Creator: unknown
Object Type: Article
System: The UNT Digital Library
Atmospheric Signals From Explosions and Their Interpretation (open access)

Atmospheric Signals From Explosions and Their Interpretation

Results are reported from a series of experimental highexplosive shots under inversion conditions at the Nevada Test Site which were made in an attempt to refine blast prediction techniques. Applications of the data in determinations of the amount of energy which remains in the blast wave as it reaches acoustic level and in determinations of the magnitude of the reflection factor when the blast wave strikes the ground are discussed. Data on shock wave propagation are presented graphically. It is concluded that the blast phenomenology of high-altitude shots can be predicted by using modified Sach's scaling. With some extrapolation to the height-of-burst versus blast-yield curve, it should be possible to make order-of-magnitude predictions of blast effects from high-altitude shots up to heights of burst of 1,000,000 ft. (C.H.)
Date: December 1, 1959
Creator: Reed, J. W.
Object Type: Report
System: The UNT Digital Library
SEFOR FOLLOW-ON PROGRAM PHASE A. Final Report, June 15, 1971--December 31, 1971 (open access)

SEFOR FOLLOW-ON PROGRAM PHASE A. Final Report, June 15, 1971--December 31, 1971

None
Date: December 31, 1972
Creator: Arterburn, J. O.
Object Type: Report
System: The UNT Digital Library
Self-mixing phenomenology in hypothetical core-disruptive accidents (open access)

Self-mixing phenomenology in hypothetical core-disruptive accidents

Physical processes are investigated that lead to the thermal equilibration of a disrupted liquid metal fast breeder reactor (LMFBR) core following a hypothetical core-disruptive accident (HCDA). Their impact is assessed, particularly as relating to the SIMMER code. The turbulent structure in the core region is characterized and bounding estimates are derived of thermal equilibration (''self-mixing'') times. The implication of these results for LMFBR safety research is discussed briefly.
Date: December 1, 1980
Creator: Chapyak, E.J.
Object Type: Report
System: The UNT Digital Library
Feasibility of beam driven semi-catalyzed deuterium fusion neutron sources for hybrid reactor applications (open access)

Feasibility of beam driven semi-catalyzed deuterium fusion neutron sources for hybrid reactor applications

The assessment is based on the estimation of the fusion device plasma properties using a simple point model, on general energy balance considerations for hybrid reactors for power generation, and on the estimation of expected performance of a specific type of hybrid reactor-a natural uranium fueled, light water moderated breeding hybrid power reactor driven by a semi-catalyzed deuterium fusion neutron source. Beam-driven semi-catalyzed deuterium and D-T fusion devices for hybrid power reactor applications are compared, and potential advantages of the former are identified. It is found that the plant efficiency of hybrid power reactors driven by a semi-catalyzed deuterium neutron source might exceed that attainable with a D-T neutron source when the fraction of the fusion neutrons that reach the blanket is smaller than about 0.8. A beam-driven deuterium fusion device can be operated in the semi-catalyzed mode and provide an intense source of neutrons even for plasma electron temperatures as low as 5 keV. Such a fusion neutron source might be useful for experimental facilities.
Date: December 1, 1977
Creator: Greenspan, E.
Object Type: Report
System: The UNT Digital Library
Quarterly Status Report on Ultra High Temperature Reactor Experiment (UHTREX) for Period Ending November 20, 1961 (open access)

Quarterly Status Report on Ultra High Temperature Reactor Experiment (UHTREX) for Period Ending November 20, 1961

The detailed design of the reactor proper was essentially completed and preparations were made for procurement of the carbon components and the pressure vessel. Design of the UHTREX facility has progressed to Titie lI. Design information is included on copper oxide beds and molecular sieves for gas cleanup. In other work, irradiation of capsules containing UHTREX fuel elements is reported along with fuel recycle research. (J.R.D.) 9578(Faye unscannable abstract)
Date: December 1, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library