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Preliminary Bibliography on the 1978-79 Intercollegiate Debate Topic.
This preliminary bibliography has been prepared for the 1978-79 Intercollegiate Debate regarding guaranteed employment.
Date:
August 15, 1978
Creator:
Roth, Dennis & Beske, Kurt
Object Type:
Report
System:
The UNT Digital Library
Thermal storage applications workshop held at Golden, Colorado, February 14-15, 1978. Volume II. Contributed papers
The 12 papers included were entered into the data base separately. (WHK)
Date:
February 15, 1979
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
(Performance evaluation of fabric bag filters on a bench-scale coal gasifier)
The objective of the proposed work is to demonstrate the operational and economic feasibility of using high-temperature ceramic filters for particulate control in a variety of coal gasification power generating systems.
Date:
January 15, 1986
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
SALT PHASE CHLORINATION OF REACTOR FUELS. IV. NIOBIUM BEHAVIOR IN THE LEAD CHLORIDE AND CHLORINE-LEAD CHLORIDE SYSTEMS
Investigation of the behavior of Nb in PbCl/sub 2/ showed that the Nb dissolution rate is quite low. Since stirring increases the rate appreciably, it is likely that the initial reaction is diffusion controlled. A subsequent reaction is linear in rate with an activation energy of 23.4 kcal per mole. Incomplete volatilization of dissolved Nb from PbCl/sub 2/ is due to the presence of lower oxidation states of Nb. The addition of Cl to PbCl/sub 2/ increases the rate of dissolution of Nb. The rate is high enough at reasonable temperatures to be practical for fuel dissolution, e.g. 12 mg min/sup -1/ cm/sup -2/ at 550 deg C and 120 mg min/sup -1/ Cl. Volatilization of NbCl/sub 5/ is 99.9% complete at 550 deg C. (auth)
Date:
March 15, 1962
Creator:
Teague, J. L.; Hahn, H. T. & Vander Wall, E. M.
Object Type:
Report
System:
The UNT Digital Library
Kilowatt isotope power system. Phase II plan. Volume V. Safety, quality assurance and reliability
The development of a Kilowatt Isotope Power System (KIPS) was begun in 1975 for the purpose of satisfying the power requirements of satellites in the 1980's. The KIPS is a /sup 238/PuO/sub 2/-fueled organic Rankine cycle turbine power system to provide a design output of 500 to 2000 W. Included in this volume are: launch and flight safety considerations; quality assurance techniques and procedures to be followed through system fabrication, assembly and inspection; and the reliability program made up of reliability prediction analysis, failure mode analysis and criticality analysis. (LCL)
Date:
March 15, 1978
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Kilowatt Isotope Power System: component test procedure for the ground demonstration system jet condenser focusing. 77-KIPS-59
This test procedure (No. 404) provides a detailed description of the verification methods which shall be used in the development program to be conducted on the Kilowatt Isotope Power System (KIPS) Jet Condenser to fulfill the requirements of the Ground Demonstration Test Plan, Section 6.4.
Date:
July 15, 1977
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Development of improved iron Fischer-Tropsch catalysts
The objective of proposed research is development of catalysts with enhanced slurry phase activity and better selectivity to fuel range products, through a more detailed understanding and systematic studies of the effects of pretreatment procedures and promoters/binders (silica) on catalyst performance.
Date:
January 15, 1990
Creator:
Bukur, D.B. & Patel, S.A.
Object Type:
Report
System:
The UNT Digital Library
GUIDE TO NUCLEAR POWER COST EVALUATION. VOLUME 4. FUEL CYCLE COSTS
Information on fuel cycle cost is presented. Topics covered include: nuclear fuel, fuel management, fuel cost, fissionable material cost, use charge, conversion and fabrication costs, processing cost, and shipping cost. (M.C.G.)
Date:
March 15, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
AN ANALYSIS TO DETERMINE THE PERCENTAGE OF HELIUM BYPASSING THE CORE DUE TO THE REFLECTOR SEALING SYSTEM DURING NORMAL OPERATION OF THE HTGR
The percentage of helium which will bypass the core if the reflector system shown is used is predicted. It is estimated that nominally about 0.1 to 0.2% of the total flow will bypass the core, which is not considered excessive. The most difficult parameter to determine was Z, the gap between the sealing surfaces. The method used to predict Z is presented. The effect of bowing due to a temperature gradient across the seals is discussed. (auth)
Date:
November 15, 1961
Creator:
Nimtz, F.B.
Object Type:
Report
System:
The UNT Digital Library
Demonstration of innovative applicatiions of technology for cost reductions to the CT-121 FGD process
The objective of this project is to demonstrate on a commercial scale several innovative applications of cost-reducing technology to the Chiyoda Thoroughbred-121 (CT-121) process. CT-121 is a second generation flue gas desulfurization (FGD) process which is considered by the Electric Power Research Institute (EPRI) and Southern Company Services (SCS) to be one of the most reliable and lowest cost FGD options for high-sulfur coal-fired utility boiler applications. Demonstrations of the innovative design approaches will further reduce the cost and provide a clear advantage to CT121 relative to competing technology.
Date:
May 15, 1991
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
LMFBR safety program. Annual technical progress report. Government fiscal year, 1977
Information is presented concerning the development of the SOMIX-1 computer code for sodium drop burning analysis; experimental analysis of burning sodium drops; aerosol leakage from containment buildings; high-temperature-concentration aerosols; aerosol source term from vaporized fuel; properties of high-temperature fuel mixtures; and development of the COMRADEX computer code for analysis of radiological doses in the environment from LMFBR accidents.
Date:
December 15, 1977
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Beam and viewing dump positioning inside TFTR for CTS alpha-particle diagnostics
A collective Thomson scattering (CTS) diagnostic system for localized measurement of energetic ions is being developed for TFTR. This system will use a 200KW, 56GHz gyrotron and a sensitive heterodyne receiver. In addition, a key element of this system will be beam and viewing dumps which are needed to minimize detection of stray gyrotron and ECE background radiation by the receiver system. It is the purpose of this study to determine the size and location of these dumps inside TFTR taking into account beam refraction and launch and receiver antenna optics scanning. The beam dump must cover all the area in the vacuum chamber where the beam is expected to impinge, and the viewing dump must cover all the areas within the direct line of sight of the receiver antenna. The beam launch system and the receiver antenna are to be placed nearly symmetrically above and below the midplane of the tokamak vacuum vessel, respectively. The beam dump is to be placed at the bottom inside of the vacuum vessel to absorb the gyrotron beam which will be launched from a top port. The viewing dump is expected to be placed symmetrically at the top inside of the vacuum vessel, …
Date:
July 15, 1991
Creator:
Rhee, D.Y.; Woskov, P.P. (Massachusetts Inst. of Tech., Cambridge, MA (United States). Plasma Fusion Center); Ellis, R. & Park, H. (Princeton Univ., NJ (United States). Plasma Physics Lab.)
Object Type:
Report
System:
The UNT Digital Library
CDC 7600 LTSS programming stratagens: preparing your first production code for the Livermore Timesharing System
This report deals with some techniques in applied programming using the Livermore Timesharing System (LTSS) on the CDC 7600 computers at the National Magnetic Fusion Energy Computer Center (NMFECC) and the Lawrence Livermore Laboratory Computer Center (LLLCC or Octopus network). This report is based on a document originally written specifically about the system as it is implemented at NMFECC but has been revised to accommodate differences between LLLCC and NMFECC implementations. Topics include: maintaining programs, debugging, recovering from system crashes, and using the central processing unit, memory, and input/output devices efficiently and economically. Routines that aid in these procedures are mentioned. The companion report, UCID-17556, An LTSS Compendium, discusses the hardware and operating system and should be read before reading this report.
Date:
August 15, 1977
Creator:
Fong, K. W.
Object Type:
Report
System:
The UNT Digital Library
Introduction to nuclear test engineering
The basic information in this report is from a vu-graph presentation prepared to acquaint new or prospective employees with the Nuclear Test Engineering Division (NTED). Additional information has been added here to enhance a reader's understanding when reviewing the material after hearing the presentation, or in lieu of attending a presentation.
Date:
July 15, 1982
Creator:
O'Neal, W.C. & Paquette, D.L.
Object Type:
Report
System:
The UNT Digital Library
Heavy leptons at the SSC
It is argued that detection of heavy leptons at the Superconducting Super Collider seems to be very difficult but perhaps not impossible. The feasibility is shown to depend critically upon the ability to identify events with W's decaying hadronically and missing transverse momentum. (LEW)
Date:
December 15, 1987
Creator:
Anderson, G. & Hinchliffe, I.
Object Type:
Article
System:
The UNT Digital Library
Development of Evaluation Techniques for Electrochemical Energy Storage Systems: Final Report
The development of standardized techniques for the comparative evaluation of electric vehicle battery technologies is summarized. The methodology considers both the traditional measures of battery performance (energy density, energy storage costs, and cycle life) and the equally important usage related battery characteristics (probability of technical success, operating and maintenance parameters, and safety/environmental impact). This comparative rationale is supplemented by the ability to generate battery test programs normalized to specific technologies and electric vehicle mission specifications. These test programs allow the evaluation of different battery technologies at comparable levels of electric vehicle performance. It was found that cost optimized electric passenger vehicles will have range specifications of 100 to 110 KM, depending on the specific performance of the battery. Longer range vehicles are penalized by higher first costs while shorter range vehicles suffer from reduced battery life and the need for more frequent alternative car rentals (presumably petroleum fueled) for trips which exceed the EV's range capability.
Date:
March 15, 1980
Creator:
Gaines, Lewis H. & Nazimek, Kenneth
Object Type:
Report
System:
The UNT Digital Library
RMDF leach-field decontamination. Final report
The objective of the decontamination effort was to place the Radioactive Materials Disposal Facility (RMDF) leach field in a condition suitable for release for unrestricted use. Radioactively contaminated soil was excavated from the leach field to produce a condition of contamination as low as reasonably achievable (ALARA). The contaminated soil was boxed and shipped to an NRC-licensed burial site at Beatty, Nevada, and to the DOE burial site at Hanford, Washington. The soil excavation project successfully reduced the contamination level in the leach field to background levels, except for less than 0.6 mCi of Sr-90 and trace amounts of Cs-137 that are isolated in cracks in the bedrock. The cracks are greater than 10 ft below the surface and have been sealed with a bituminous asphalt mastic. A pathways analysis for radiation exposure to humans from the remaining radionuclides was performed, assuming intensive home gardening, and the results show that the total first year whole body dose equivalent would be about 0.1 mrem/year. This dose equivalent is a projection for the hypothetical ingestion of vegetables grown on the site. Assuming that an average adult consumes 64 kg of green leafy vegetables per year and that the entire yearly supply could …
Date:
September 15, 1982
Creator:
Carroll, J W; Marzec, J M & Stelle, A M
Object Type:
Report
System:
The UNT Digital Library
REACTOR FUEL WASTE DISPOSAL PROJECT PRESSURE-TEMPERATURE EFFECT ON SALT CAVITIES AND SURVEY OF LIQUEFIED PETROLEUM GAS STORAGE
It is deemed feasible to store reactor fuel wastes in a salt dome cavity to a depth where the differential in pressure between the soil over-burden pressure and pressure of the fluid inside the cavity does not exceed 3000 psi, and the temperature is less than 400 deg F. Tests at pressure increments of 1000 psi were conducted on a 2" cylindrical cavity contained in a 6-in. long by 6-in. cylindrical salt core. Tests indicate that the cavity exhibited complete stability under pressures to 3000 psi and temperatures to 300 deg F. At temperatures of 100 to 400 deg F and pressures to 5000 psi continuous deformation of the cavity resulted. Initial movement of the salt was observed at all pressures. This was evidenced by vertical deformation and cavity size reduction. It was noted that a point of structural equilibrium was reached at lower temperatures when the pressure did not exceed 5000 psi. A literature study reveals that the most common type of cavity utilized in liquefied petroleum gas storage is either cylindrical or ellipsoidal. A few are pear or inverted cone shaped. There was no indication of leakage for cavities when pressure tested for as long as 72 hr. …
Date:
January 15, 1959
Creator:
Brown, K. E.; Jessen, F. W. & Gloyna, E. F.
Object Type:
Report
System:
The UNT Digital Library
Weld Penetration and Defect Control
Highly engineered designs increasingly require the use of improved materials and sophisticated manufacturing techniques. To obtain optimal performance from these engineered products, improved weld properties and joint reliability are a necessarily. This requirement for improved weld performance and reliability has led to the development of high-performance welding systems in which pre-programmed parameters are specified before any welding takes place. These automated systems however lack the ability to compensate for perturbations which arise during the welding process. Hence the need for systems which monitor and control the in-process status of the welding process. This report discusses work carried out on weld penetration indicators and the feasibility of using these indicators for on-line penetration control.
Date:
May 15, 1992
Creator:
Chin, Bryan A.
Object Type:
Report
System:
The UNT Digital Library
(Performance evaluation of fabric bag filters on a bench-scale coal gasifier)
The objective of the proposed work is to demonstrate the operational and economic feasibility of using high-temperature ceramic filters for particulate control in a variety of coal gasification power generating systems.
Date:
January 15, 1986
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
VOID COEFFICIENT OF REACTIVITY ASSOCIATED WITH THE ISLAND REGION OF THE HFIR
Changes in neutron multiplication caused by voids in the island of the HFlR were calculated and measured experimentally. The results indicated that with only water initially in the island the maximum change in neutron multiplication ( DELTA k/sub max) associated with island voids is 0.032 with a corresponding void fraction of 70%. With a simulated 300 g Pu target in the island DELTA k/sub max/ was 0.0l6, and the corresponding void fraction was 42%. In view of these large changes in neutron multiplication, calculations were made to determine what additional materials could be used in the island to reduce DELTA k/sub max/ and what the associated decrease in peak thermal flux wouId be. The results indicated that of the materials considered the use of beryllium in the water island resulted in the smallest decrease in flux for a specified DELTA k/sub max/. To reduce DELTA k/sub max/ to 0.01 required 26% by volume of beryllium in the island; the corresponding reduction in thermal flux, as compared to an all-water island, was about 10%. In order to reduce DELTA k/sub max/ to 0.0l with a 300 g Pu target in the island, the aIuminum-to-water ratio of the target had to be …
Date:
November 15, 1961
Creator:
Cheverton, R.D.
Object Type:
Report
System:
The UNT Digital Library
STEAM-COOLED POWER REACTOR EVALUATION, STEAM-COOLED FAST BREEDER REACTOR
Conceptual design and economic studies of a steamcooled fast breeder reactor that can also be used as a source of power are presented. Two reactor plant sizes were considered: a 300-Mw(e) central power station plant and a 40 Mw(e) plant. It was concluded that attractive economics and good breeding characteristics breeding ratios from 1.27 to 1.42) can be achieved in steam- cooled PuO/sub 2/UO/sub 2/ fueled fast reactors. Low capital costs can be obtained by a compact reactor core and the absence of large heat exchangers and complicated process systems. Reactor design data are discussed. Analysis showed that these reactors can be prevented from going prompt critical, when fully flooded, by incorporating a tolerable amount of high resonance absorption materials such as hafnium or indium. An increase in reactivity on loss of coolant was indicated by preliminary calculations. (M.C.G.)
Date:
April 15, 1961
Creator:
Sofer, G.; Hankel, R.; Goldstein, L. & Birman, G.
Object Type:
Report
System:
The UNT Digital Library
SNAP II POWER CONVERSION SYSTEM TOPICAL REPORT NO. 11, ORBITAL FORCE FIELD BOILING AND CONDENSING EXPERIMENT
The characteristics of Rankine space power plants in the zero gravity aspect of the environment of space were lnvestigated. The expected effects of Rankine space power plants are described. Discussions of experimental techniques for studying these phenomena show that this information can be obtained rapidly and economically. Recommendations for a program to supplement SNAP II and slmllar Ranklne space power development efforts in this vital area are made, and consist of: the development and testing of a small system that adequately simulates a complete Ranklne system, first in zero grayity and finally, in the complete orbltal environment; followed by, the development and similar testing of a complete Rankine system using SNAP ll hardware. (auth)
Date:
January 15, 1960
Creator:
Grevstad, P.E.
Object Type:
Report
System:
The UNT Digital Library
AN INFORMATION STORAGE AND RETRIEVAL SYSTEM FOR IRRADIATION EFFECTS IN METALS
An information storage and retrieval system (PIC) was developed, utilizing the IBM 7090 computer, for handling data pertaining to the effects of neutron irradiation on metals. The input includes a reference identification, an appropriate abstract or extract summarizing the article, code identification parameters analogous to those used by the ASM-SLA Literature Classification System, and special codes identifying relevant irradiation and testing parameters. The output contains the same data plus printing out the meaning of all special codes. Presently, the information storage consists of more than two hundred references representing several thousand lines of information. The system is both general and definitive, permitting the selection of a single piece of information or of many references dealing with a general field. It is possible to select material on the basis of one or more of the following factors: material, general or specific; type of literature; general or specific property such as mechanical tests or tensile tests; conditions of irradiation including type and level of flux, integrated flux, irradiation temperature, and reactor environment; test conditions such as temperature and environment; and general variables that might be controlling such as strain rate, specimen geometry, grain size, and fabrication history. It is felt that this …
Date:
August 15, 1963
Creator:
Bush, S. H.
Object Type:
Article
System:
The UNT Digital Library