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795
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95
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83
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50
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39
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Particle Accelerator Division Summary Report, April Through September 1960
Work is summarized in the areas of orbit theory, injector studies, ring magnet systems development, vacuum system development, the radio-frequency system, beam extraction, and targetry. (B.O.G.)
Date:
October 31, 1962
Creator:
unknown
System:
The UNT Digital Library
Proceedings of the International Conference on Sodium Technology and Large Fast Reactor Design, November 7--9, 1968. Part Ii. Sessions on Large Fast Reactor Design.
None
Date:
October 31, 1969
Creator:
unknown
System:
The UNT Digital Library
Engineering assessment of inactive uranium mill tailings, Shiprock site, Shiprock, New Mexico. Phase II, Title I
Ford, Bacon and Davis Utah Inc. has performed an engineering assessment of the problems resulting from the existence of radioactive uranium mill tailings at Shiprock, New Mexico. The Phase II, Title I services include the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and other radium-contaminated materials, the evaluation of resulting radiation exposures of individuals and nearby populations, the investigation of site hydrology and meteorology and the evaluation and costing of alternative corrective actions. Radon gas release from the 1.7 million tons of tailings at the Shiprock site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation are also factors. The 11 alternative actions presented range from completion of the present ongoing EPA site decontamination plan (Option I), to stabilizing in-place with varying depths of cover material (Options II-IV), to removal to an isolated long-term disposal site (Options V-XI). All options include remedial action costs for off-site locations where tailings have been placed. Costs estimates for the 11 options range from $540,000 to $12,500,000. Reprocessing the tailings for uranium is not economically feasible.
Date:
March 31, 1977
Creator:
unknown
System:
The UNT Digital Library
JBK-75 microstructure specification recommendation. [Modified A-286]
Since the ASTM-E-45 standard for microcleanliness is not applicable to superalloys like JBK-75 stainless steel (Modified A-286), Rocky Flats should adopt the Ladish microcleanliness standard (APML Cleanliness Classification of High Temperature Alloys Chart, 1971), as a guide for setting material acceptance specifications for JBK-75. Inclusion ratings of S-2, N-2, C-2, and M-2 should be acceptable. The microstructure should have a grain size of 5 or finer, but not smaller than 9, and microsegregation (banding) should be kept to a minimum.
Date:
October 31, 1977
Creator:
Brewer, A. W.
System:
The UNT Digital Library
Hydrogeochemical and stream sediment reconnaissance basic data for Carlsbad quadrangle, New Mexico
Field and laboratory data are presented for 467 water samples and 1680 sediment samples from the Carlsbad Quadrangle, New Mexico. The samples were collected and uranium analysis performed by Los Alamos National Laboratory; multielement analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee.
Date:
August 31, 1981
Creator:
unknown
System:
The UNT Digital Library
Brayton-cycle heat recovery-system characterization program. Subatmospheric-system test report
The turbine tests and results for the Brayton cycle subatmospheric system (SAS) are summarized. A scaled model turbine was operated in the same environment as that which a full-scale SAS machine would experience from the hot effluent flue gas from a glass container furnace. The objective of the testing was to evaluate the effects of a simulated furnace flue gas stream on the turbine nozzles and blades. The following specific areas were evaluated: erosion of the turbine nozzles and blades from the dust in the flue gas, hot corrosion from alkali metal salts in the dust and acid vapor (sulfur trioxide and hydrogen chloride) in the flue gas, and fouling and flow blockage due to deposition and/or condensation from the flue gas constituents.
Date:
July 31, 1981
Creator:
Burgmeier, L. & Leung, S.
System:
The UNT Digital Library
Flow visualizations, velocity measurements, and surface convection measurements in simulated 20. 8-cm Nova box amplifier cavities
Reported are fluid mechanics experiments performed in models of the 20.8-cm Nova amplifier lamp and disk cavities. Lamp cavity nitrogen flows are shown, by both flow visualization and velocity measurements, to be acceptably uniform and parallel to the flashlamps. In contrast, the nitrogen flows in the disk cavity are shown to be disordered. Even though disk cavity flows are disordered, the simplest of three proposed nitrogen introduction systems for the disk cavity was found to be acceptable based on convection measurements made at the surfaces of simulated laser disks.
Date:
October 31, 1983
Creator:
Julien, J.L. & Molishever, E.L.
System:
The UNT Digital Library
Thermoelectric materials evaluation program spring design to minimize load relaxation
The recommended spring material for use in thermoelectric modules is either Inconel x or Elgiloy based on their excellent performance and availability. The stress level for generator applications is 75,000 psi. (FS)
Date:
March 31, 1980
Creator:
Grimm, F.R.
System:
The UNT Digital Library
District heating and cooling systems for communities through power plant retrofit distribution network. Phase 2. Final report, 1 March 1980-31 January 1984. Volume VII. Appendix C
This volume contains: Hudson No. 2 Limited Retrofit Cost Estimates provided by Stone and Webster Engineering Corp. (SWEC); backup data and basis of estimate for SWEC Heater Plant and Gas Turbine Plant (Kearny No. 12) cost estimates; and Appendices - Analysis of Relevant Tax Laws.
Date:
January 31, 1984
Creator:
unknown
System:
The UNT Digital Library
Development of high efficiency cascade solar cells. Quarterly technical progress report No. 3
Progress is reported in the following areas: AlGaAsSb/GaAsSb materials development, GaInP materials development via VPE, GaAlAs/GaAs cell development, and OM/CVD studies. Spectral response, V-I characteristics, and electron microprobe analysis results are presented. (WHK)
Date:
March 31, 1980
Creator:
unknown
System:
The UNT Digital Library
Assessment of underground coal gasification in bituminous coals: potential UCG products and markets. Final report, Phase I
The following conclusions were drawn from the study: (1) The US will continue to require new sources of energy fuels and substitutes for petrochemical feedstocks into the foreseeable future. Most of this requirement will be met using coal. However, the cost of mining, transporting, cleaning, and preparing coal, disposing of ash or slag and scrubbing stack gases continues to rise; particularly, in the Eastern US where the need is greatest. UCG avoids these pitfalls and, as such, should be considered a viable alternative to the mining of deeper coals. (2) Of the two possible product gases LBG and MBG, MBG is the most versatile. (3) The most logical use for UCG product in the Eastern US is to generate power on-site using a combined-cycle or co-generation system. Either low or medium Btu gas (LBG or MBG) can be used. (4) UCG should be an option whenever surface gasification is considered; particularly, in areas where deeper, higher sulfur coal is located. (5) There are environmental and social benefits to use of UCG over surface gasification in the Eastern US. (6) A site could be chosen almost anywhere in the Illinois and Ohio area where amenable UCG coal has been determined due …
Date:
January 31, 1982
Creator:
unknown
System:
The UNT Digital Library
Chemical and thermal stability of refrigerant-lubricant mixture with metal
This report presents completed sealed tube stability test results for the R-123/mineral oil mixture and preliminary results for seven of the eighteen contracted refrigerant-lubricant mixtures. The R-123 mixture was tested at 105, 150, and 175{degrees}C. The results obtained indicate that prolonged exposure to temperatures of about 150{degree}C and higher will lead to rapid chemical deterioration of the R-123/mineral oil system. Chlorotrifluoroethane (R-133a) and trifluoroethane (R-143a) have been identified as decomposition products of R-123. Testing at 150 and 175{degrees}C have been completed for the HCFC refrigerants R-22, R-124, and R-142b with either mineral oil or alkylbenzene lubricants. These mixtures were very stable at the indicated temperatures. Testing at a higher temperature level will be necessary to define their upper temperature limits. Similarily, partial test results are available for HFC refrigerants R-32, R-125, R-134a (two esters), and R-143a with pentaerythritol ester lubricants at the 150 and 175{degrees}C temperature levels. Again, all five mixtures were found to be extremely stable at the test temperatures and additional testing will be needed to establish their upper temperature limits.
Date:
March 31, 1992
Creator:
Huttenlocher, D.F. (Spauschus Associates, Inc., Atlanta, GA (United States))
System:
The UNT Digital Library
Engineering assessment of inactive uranium mill tailings, Monument Valley site, Monument Valley, Arizona. A summary of the Phase II, Title I
Ford, Bacon and Davis Utah Inc. has performed an engineering assessment of the problems resulting from the existence of radioactive uranium mill tailings at the Monument Valley millsite in Arizona. The Phase II, Title I services include the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and other radium-contaminated materials, the evaluation of resulting radiation exposures of individuals residing nearby, the investigation of site hydrology and meteorology and the evaluation and costing of alternative corrective actions. Radon gas release from the tailings on the site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation are also factors. The sparse population and relatively low radiation levels yield minimal immediate environmental impact; hence, the two alternative actions presented are directed towards restricting access to the site (Options I and II), and returning the windblown tailings to the pile and stabilizing the pile with 2 ft of cover material (Option II). Both options include remedial action costs for offsite locations where tailings have been placed. Cost estimates for the two options are $585,000 and $1,165,000. Reprocessing the tailings for uranium is not economically feasible.
Date:
March 31, 1977
Creator:
unknown
System:
The UNT Digital Library
CYCLOTRON LABORATORY ANNUAL REPORT, MARCH 1, 1971--May 1, 1972
None
Date:
December 31, 1972
Creator:
unknown
System:
The UNT Digital Library
Fuel Cycle Program, a Boiling Water Reactor Research and Development Program. Third Quarterly Report, January 1961-March 1961
The continuing analysis of the VBWR core resulted in refinements in the calculations for reactivity in voids, flux leakage and resonance escape probability. The Zircaloy cladding for 25 fuel assemblies was received and passed inspection. Preliminary measurements of VBWR flux oscillations, used to develop instrumentation and data interpretation techniques, showed random normally-distributed oscillations with a predominant frequency of 0.5 to 1.0 cycles/second. A model for analog computer simulation of a reactor as a feedback control system was adapted to VBWR. Equations for the hydraulics model and preliminary results from use of the model are presented. Irradiation of the Fuel Cycle stainless steel clad assemblies reached 412 MWD/T with specific powers of 28 kw/kg (average) and 52 kw/kg (peak) during January. Visual examination of the fuel after this irradiation indicated that it is in good condition. The VBWR was shut down during February and March for replacement of all in-core components made of 17-4 pH stainless steel with 304 stainless steel. The details of the first eight special fuel assemblies were determined and materials were ordered. The effects of steam quality, mass flow rate, and rod diameter on burnout heat flux are shown. The burnout heat flux varied inversely with mass …
Date:
October 31, 1961
Creator:
unknown
System:
The UNT Digital Library
K$sup +$d INTERACTIONS FROM 865 TO 1365 MeV/c
None
Date:
December 31, 1970
Creator:
Hirata, A. A.
System:
The UNT Digital Library
PHYSICS DIVISION SUMMARY REPORT. Annual Review, April 1, 1967--March 31, 1968
None
Date:
August 31, 1969
Creator:
Bollinger, L.M.
System:
The UNT Digital Library
ROVER ROCKET MATERIALS.
None
Date:
October 31, 1969
Creator:
Clausing, R.E.
System:
The UNT Digital Library
THERMAL, STRUCTURAL, AND MAGNETIC STUDIES OF METALS AND INTERMETALLIC COMPOUNDS. Annual Report, May 15, 1971--May 15, 1972
None
Date:
December 31, 1972
Creator:
Wallace, W E & Craig, R S
System:
The UNT Digital Library
STUDIES OF NUCLEAR FISSION, LOW-ENERGY NUCLEAR REACTIONS AND TRANSURANIC NUCLEI. Progress Report, June 1, 1971--June 1, 1972
None
Date:
December 31, 1972
Creator:
Huizenga, J.R.
System:
The UNT Digital Library
Demonstration plant supplementary technical studies section 10-confidence analysis. SRC-II demonstration project, phase zero, task number 1, deliverable number 3
The Gulf Management Sciences Group (GMSG) in Pittsburgh was asked to provide assistance in performing a confidence analysis for the SRC-II demonstration plant as required by the Department of Energy. Specifically, the contract says to discuss confidence levels for plant operating and capital costs; plant operability and technical risk. It was decided that the best way to obtain estimates for these variables would be through interviews of people with substantial experience in the field. Each subject was first asked what modifications he envisioned being made to the current plant design. Discussion was limited to major systems that might require partial redesign and comments concerning the plant in general. The interviewees were next asked to estimate the probability of success for the project, given that the modifications they envisioned were in fact made. The modes of the combined distributions of the interview results indicate that the respondents in general felt that the base case estimates represented the most probable outcomes with the possible exception of the capital cost estimate. On the other hand, the respondents consistently judged that there is a chance that the demonstration plant will perform significantly worse than the base case for each of the variables that were …
Date:
July 31, 1979
Creator:
unknown
System:
The UNT Digital Library
Stability of ceramic waste forms in potential repository environments: a review
Most scenarios for geologic disposal of high-level nuclear waste include the eventual intrusion of groundwater into the repository. Reactions in the system and eventual release of the radionuclides, if any, will be controlled by the chemistry of the groundwater, the surrounding rock, the waste form, and any engineered barrier materials that are present, as well as by the temperature and pressure of the system. This report is a compilation and evaluation of the work completed to date on interactions within the waste-form/host-rock/groundwater system at various points in its lifetime. General results from leaching experiments are presented as a basis for comparison. The factors involved in studying the complete system are discussed so that future research may avoid some of the oversights of past research. Although relatively little hard data on prototype waste-form/repository-system interactions exist at this time, the available data and their implications are discussed. Sorption studies and models for predicting radionuclide migration are also presented, again with a study of the factors involved.
Date:
March 31, 1982
Creator:
Johnston, R. J. & Palmer, R. A.
System:
The UNT Digital Library
Solar Pilot Plant, Phase I. Quarterly report No. 5, October--December 1976
Collector subsystem research experiment (SRE) tests were conducted and the data evaluated. Assembly of the SRE steam generator was almost complete. Testing will start in January 1977. Two major changes in the baseline design, sensible thermal heat storage rather than phase-change storage and wet rather than dry cooling of the condenser, were being worked. Analytical and design work on the electrical generation subsystem and plant integration progressed satisfactorily.
Date:
March 31, 1977
Creator:
unknown
System:
The UNT Digital Library
LOFT pressurizer surge line stress and fatigue life analysis report
A stress analysis was performed on the LOFT pressurizer surge line (hereafter called the surge line) to determine if it met the requirements of the ASME BPV Code Section III, for Class 1 components. Dead weight, thermal expansion, seismic, design LOCE and LOCA loads were considered. After the addition of restraints (specified in letter, HIK-12-75, ''LOFT Pipe Hanger Requirements on Main Feed, Main Steam, Pressurizer, and ECC Systems,'' Nov. 24, 1975) the primary and secondary stress levels were found to be acceptable.
Date:
May 31, 1977
Creator:
Muffett, J.W.
System:
The UNT Digital Library