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Experimental system and component performance analysis (open access)

Experimental system and component performance analysis

A prototype dye laser flow loop was constructed to flow test large power amplifiers in Building 169. The flow loop is designed to operate at supply pressures up to 900 psig and flow rates up to 250 GPM. During the initial startup of the flow loop experimental measurements were made to evaluate component and system performance. Three candidate dye flow loop pumps and three different pulsation dampeners were tested.
Date: October 1, 1984
Creator: Peterman, K.
Object Type: Report
System: The UNT Digital Library
Hydroacoustic Monitoring of Downstream Migrant Salmon and Steelhead at Wells Dam in Spring 1984. (open access)

Hydroacoustic Monitoring of Downstream Migrant Salmon and Steelhead at Wells Dam in Spring 1984.

The downstream migration of salmon and steelhead in spring 1984 at Wells Dam on the mid-Columbia River was monitored using hydroacoustics. The primary objective of this research was to document run timing and describe the distribution of smolts at the dam. The study occurred from April 2 to June 15, 1984. Four transducers were deployed at the bases of pier noses at Turbines 3, 5, 7, and 9 and aimed up 24/sup 0/ into the forebay. They were sampled once every hour, 24 hours per day, for 75 days. An index of fish passage was reported daily to the Water Budget Center in Portland, Oregon. This index was computed as follows. For each 24-h period, separate fish passage rates (number/time) at each of the four sampling locations were estimated by dividing the sum of the ''weighted'' fish detections by total sample time. These four values then were averaged to produced the daily index (number/day/location). The first substantial increase in fish passage occurred on April 25, 1984 due to the chinook released from the Winthrop hatchery on April 23. During May, run timing was fairly uniform except for peaks on May 2, 14, 18, and 22. The unexpected peak in run …
Date: October 31, 1984
Creator: Raemhild, Gary A.
Object Type: Report
System: The UNT Digital Library
Avoiding Leakage Flow-Induced Vibration by a Tube-in-Tube Slip Joint (open access)

Avoiding Leakage Flow-Induced Vibration by a Tube-in-Tube Slip Joint

Parameters and operating conditions (a stability map) were determined for which a specific slip-joint design did not cause self-excited lateral vibration of the two cantilevered, telescoping tubes forming the joint. The joint design featured a localized annular constriction. Flowrate, modal damping, tube engagement length, and eccentric positioning were among the parameters tested. Interestingly, all self-excited vibrations could be avoided by following a simple design rule: place constrictions only at the downstream end of the annular region between the tubes. Also, overall modal damping decreased with increased flowrate, at least initially, for upstream constrictions while the damping increased for downstream constrictions.
Date: October 1984
Creator: Mulcahy, T. M.
Object Type: Report
System: The UNT Digital Library
Second Thoughts on the Mathematical Software Effort : a Perspective (open access)

Second Thoughts on the Mathematical Software Effort : a Perspective

The mathematical software effort bridges the gap between the discovery of numerical algorithms and the consumption of numerical software. The spectrum of activities is surprisingly wide, including tasks often associated with numerical analysis, program design and testing, programming practices, language standards, documentation standards, software organization, distribution methods, and even the specification of arithmetic engines. This paper highlights the most important accomplishments in the field over the last twenty years. It also examines current problems and future challenges posed by the rapid advance of technology.
Date: October 1984
Creator: Cody, William James
Object Type: Report
System: The UNT Digital Library
Nuclear Technology Programs Quarterly Progress Report: January-March 1984 (open access)

Nuclear Technology Programs Quarterly Progress Report: January-March 1984

Quarterly report on activities of Argonne National Laboratory's Nuclear Technical Programs, including studies on nuclear fuels and nuclear waste.
Date: October 1984
Creator: Steindler, M. J.
Object Type: Report
System: The UNT Digital Library
Pagosa Springs geothermal project. Final technical report (open access)

Pagosa Springs geothermal project. Final technical report

This booklet discusses some ideas and methods for using Colorado geothermal energy. A project installed in Pagosa Springs, which consists of a pipeline laid down 8th street with service to residences retrofitted to geothermal space heating, is described. (ACR)
Date: October 19, 1984
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Advanced Thermionic Technology Program: summary report. Volume 4. Final report (open access)

Advanced Thermionic Technology Program: summary report. Volume 4. Final report

This report summarizes the progress made by the Advanced Thermionic Technology Program during the past several years. This Program, sponsored by the US Department of Energy, has had as its goal adapting thermionic devices to generate electricity in a terrestrial (i.e., combustion) environment. Volume 4 (Part E) is a highly technical discussion of the attempts made by the Program to push the state-of-the-art beyond the current generation of converters and is directed toward potential researchers engaged in this same task. These technical discussions are complemented with Appendices where appropriate.
Date: October 1, 1984
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Flibe/He concept (open access)

Flibe/He concept

As in all fusion blankets many physics and engineering parameters influence material temperature and heat transfer to the coolant. In performing thermal-hydraulics calculations for the Flibe/He concept, the first wall was assumed to be 5 MW/m/sup 2/. The coolant is helium with a nominal pressure of 50 atmospheres. To eliminate ''pinch-point'' steam generator problems a helium inlet temperature of 275/sup 0/C was specified. Helium outlet temperature was limited to 500/sup 0/C in order to not have structural HT-9 steel above 550/sup 0/C. That limit for HT-9 has been imposed due to neutron damage effects which seriously detract from its ductility and strength above that temperature. Volumetric heating calculations at various blanket locations are given.
Date: October 1, 1984
Creator: Moir, R.
Object Type: Report
System: The UNT Digital Library
Shock waves, increase of entropy and loss of information (open access)

Shock waves, increase of entropy and loss of information

We discuss, for the simplified model of a single conservation law, the concepts of genuine nonlinearity, breakdown of classical solutions, solutions in the distribution sense and their nonuniqueness, the viscosity method, finite difference methods, and the shock condition. We then discuss, for the scalar model, the compactness of solutions constructed by the viscosity and difference methods, and derive the entropy inequality for such solutions. We derive Glimm's estimate for the total variation of solutions of scalar equations that satisfy the shock condition, and show that a discontinuous solution that satisfies the shock condition also satisfies the entropy condition. Scattered remarks are given about the equations of compressible flow: the increase of entropy, some consequences of Carnot's theorem, and the equipartition of energy in the wake of strong shocks.
Date: October 1, 1984
Creator: Lax, P.D.
Object Type: Report
System: The UNT Digital Library
FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume I (open access)

FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume I

The following chapters are included in this study: (1) fusion nuclear issues, (2) survey of experimental needs, (3) requirements of the experiments, (4) non-fusion facilities, (5) fusion facilities for nuclear experiments, and (6) fusion research and development scenarios. (MOW)
Date: October 1, 1984
Creator: Abdou, M.
Object Type: Report
System: The UNT Digital Library
Advanced Thermionic Technology Program: summary report. Volume 1. Final report (open access)

Advanced Thermionic Technology Program: summary report. Volume 1. Final report

This report summarizes the progress made by the Advanced Thermionic Technology Program during the past several years. This program, sponsored by the US Department of Energy, has had as its goal adapting thermionic devices to generate electricity in a terrestrial (i.e., combustion) environment. The technology has previously been developed for astronautical applications. The report is organized in four volumes, each focused as much as possible on the needs of a particular audience. Volume 1 contains Part A, the Executive Summary. This Executive Summary describes the accomplishments of the Program in brief, but assumes the reader's familiarity with the thermionic process and the technical issues associated with the Program. For this reason, Volume 1 also contains Part B, a minimally technical overview of the Advanced Thermionic Technology Program. Volume 2 (Part C) concentrates on the progress made in developing and fabricating the ''current generation'' of chemical vapor deposited hot shell thermionic converters and is addressed to those primarily concerned with today's capabilities in terrestrial thermionic technology. Volume 3 (Part D) contains the results of systems studies of primary interest to those involved in identifying and evaluating applications for thermionics. Volume 4 (Part E) is a highly technical discussion of the attempts …
Date: October 1, 1984
Creator: unknown
Object Type: Report
System: The UNT Digital Library
FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume II (open access)

FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume II

The Nuclear Fusion Issues chapter contains a comprehensive list of engineering issues for fusion reactor nuclear components. The list explicitly defines the uncertainties associated with the engineering option of a fusion reactor and addresses the potential consequences resulting from each issue. The next chapter identifies the fusion nuclear technology testing needs up to the engineering demonstration stage. (MOW)
Date: October 1, 1984
Creator: Abdou, M.
Object Type: Report
System: The UNT Digital Library
Southwest Retort, Volume 37, Number 2, October 1984 (open access)

Southwest Retort, Volume 37, Number 2, October 1984

This publication of the Dallas-Fort Worth Section of the American Chemical Society includes information about research, prominent scientist, organizational business, and various other stories of interest to the community.
Date: October 1984
Creator: American Chemical Society. Dallas/Fort Worth Section.
Object Type: Journal/Magazine/Newsletter
System: The UNT Digital Library
The Tulia Herald (Tulia, Tex.), Vol. 76, No. 41, Ed. 1 Thursday, October 11, 1984 (open access)

The Tulia Herald (Tulia, Tex.), Vol. 76, No. 41, Ed. 1 Thursday, October 11, 1984

Weekly newspaper from Tulia, Texas that includes local, state and national news along with extensive advertising.
Date: October 11, 1984
Creator: Tooley, Wendell
Object Type: Newspaper
System: The Portal to Texas History
The Tulia Herald (Tulia, Tex.), Vol. 76, No. 43, Ed. 1 Thursday, October 25, 1984 (open access)

The Tulia Herald (Tulia, Tex.), Vol. 76, No. 43, Ed. 1 Thursday, October 25, 1984

Weekly newspaper from Tulia, Texas that includes local, state and national news along with extensive advertising.
Date: October 25, 1984
Creator: Tooley, Wendell
Object Type: Newspaper
System: The Portal to Texas History
The Tulia Herald (Tulia, Tex.), Vol. 76, No. 40, Ed. 1 Thursday, October 4, 1984 (open access)

The Tulia Herald (Tulia, Tex.), Vol. 76, No. 40, Ed. 1 Thursday, October 4, 1984

Weekly newspaper from Tulia, Texas that includes local, state and national news along with extensive advertising.
Date: October 4, 1984
Creator: Tooley, Wendell
Object Type: Newspaper
System: The Portal to Texas History
The Tulia Herald (Tulia, Tex.), Vol. 76, No. 42, Ed. 1 Thursday, October 18, 1984 (open access)

The Tulia Herald (Tulia, Tex.), Vol. 76, No. 42, Ed. 1 Thursday, October 18, 1984

Weekly newspaper from Tulia, Texas that includes local, state and national news along with extensive advertising.
Date: October 18, 1984
Creator: Tooley, Wendell
Object Type: Newspaper
System: The Portal to Texas History
Vanadium-base alloys for fusion reactor applications (open access)

Vanadium-base alloys for fusion reactor applications

Vanadium-base alloys offer potentially significant advantages over other candidate alloys as a structural material for fusion reactor first wall/blanket applications. Although the data base is more limited than that for the other leading candidate structural materials, viz., austenitic and ferritic steels, vanadium-base alloys exhibit several properties that make them particularly attractive for the fusion reactor environment. This paper presents a review of the structural material requirements, a summary of the materials data base for selected vanadium-base alloys, and a comparison of projected performance characteristics compared to other candidate alloys. Also, critical research and development (R and D) needs are defined.
Date: October 1, 1984
Creator: Smith, D. L.; Loomis, B. A. & Diercks, D. R.
Object Type: Article
System: The UNT Digital Library
In situ vitrification pilot-scale radioactive test (open access)

In situ vitrification pilot-scale radioactive test

Pacific Northwest Laboratory (PNL) is developing in situ vitrification (ISV) as an in-place stabilization technique for selected liquid radioactive waste disposal sites. The process melts the wastes and surrounding soil to produce a durable glass and crystalline waste form. These ISV process development testing and evaluation studies are being conducted for the US Department of Energy. The results of an ISV pilot-scale test conducted in June of 1983 in which soils contaminated with actual radioactive transuranic and mixed fission product elements were vitrified are discussed. The primary objectives of the radioactive test were to: demonstrate containment and confinement of the radioactive material; verify equipment performance of the power and off-gas systems; identify losses to the off-gas system; and characterize the behavior of the radioactive material in the vitrified soil. The test successfully demonstrated the processing containment of radionuclides both within the vitrified mass and in the off-gas system. No environmental release of radioactive material was measured during testing operations. The vitrified soil had a greater than 99% retention of all radionuclides. Losses to the off-gas system varied from less than or equal to 0.03% for particulate materials (plutonium and strontium) to 0.8% for cesium which is a more volatile element. …
Date: October 1, 1984
Creator: Timmerman, C.L. & Oma, K.H.
Object Type: Report
System: The UNT Digital Library
Kinetic analysis of MHD ballooning modes in tokamaks (open access)

Kinetic analysis of MHD ballooning modes in tokamaks

A comprehensive analysis of the stability properties of the appropriate kinetically generalized form of MHD ballooning modes together with the usual trapped-particle drift modes is presented. The calculations are fully electromagnetic and include the complete dynamics associated with compressional ion acoustic waves. Trapped-particle effects along with all forms of collisionless dissipation are taken into account without approximations. The influence of collisions is estimated with a model Krook operator. Results from the application of this analysis to realistic tokamak operating conditions indicate that unstable short-wavelength modes with significant growth rates can extend from ..beta.. = 0 to value above the upper ideal-MHD-critical-beta associated with the so-called second stability regime. Since the strength of the relevant modes appears to vary gradually with ..beta.., these results support a soft beta limit picture involving a continuous (rather than abrupt or hard) modification of anomalous transport already present in low-..beta..-tokamaks. However, at higher beta the increasing dominance of the electromagnetic component of the perturbations indicated by these calculations could also imply significantly different transport scaling properties.
Date: October 1, 1984
Creator: Tang, W. M.; Rewoldt, G.; Cheng, C. Z. & Chance, M. S.
Object Type: Report
System: The UNT Digital Library
Magnetism and Superconductivity in Eu(Ho)Mo/sub 6/S/sub 8/ (open access)

Magnetism and Superconductivity in Eu(Ho)Mo/sub 6/S/sub 8/

A variety of ambient and high pressure experimental results reveal the interplay between magnetism and superconductivity in Ho doped samples of the pressure induced superconductor, EuMo/sub 6/S/sub 8/. Ho concentrations up to 50 atomic percent of the rare earth ions were used. High resolution magnetic measurements are consistent with the crystalline electric field ground state for the Ho/sup 3 +/ ions being a magnetic doublet consisting largely of J/sub z/ = 18. The results of high pressure magnetization experiments reveal negligible effects of reduced lattice constant on the rare earth-rare earth interactions. Resistivity in a 10 atomic percent sample for P = 10 kbar shows the suppression of a P = 0 structural transition, metallic conductivity down to low temperatures, and finally superconductivity at 8 K. The upper critical field, H/sub c2/(T), for this sample was measured for P = 7, 10 and 12 kbar and showed strong reentrant behavior (dH/sub c2/(T)/dT > 0 as T ..-->.. 0 K). A minimum with field in the resistivity above H/sub c2/ was also observed at lowest temperatures. The H/sub c2/(T) data are compared with those of EuMo/sub 6/S/sub 8/ at high pressure, which shows positive curvature, and HoMo/sub 6/S/sub 8/, in which …
Date: October 1, 1984
Creator: Capone, D. W., II; Lai Fook, M. S.; Guertin, R. P.; Hinks, D. G.; Dunlap, B. D.; Foner, S. et al.
Object Type: Article
System: The UNT Digital Library
First order leveling: Pleasant Bayou geothermal test site, Brazoria County, Texas (open access)

First order leveling: Pleasant Bayou geothermal test site, Brazoria County, Texas

First order leveling to be conducted as part of an environmental monitoring program for a geopressured test well was reported. 39.43 kilometers of first order levels were run to NGS specifications. Twelve Class B type bench marks were set to NGS specifications. The adjusted elevation of bench mark C-1209 was used as a starting elevation and is based on a supplementary adjustment of April 6, 1979 by NGS. The closure for the loop around the well site is -0.65 millimeters. The distance around the loop is 1.29 kilometers, the allowable error of closure was 4.54 millimeters. The initial leveling of this well was performed in 1977. A thorough search for their monumentation was conducted. No monuments were found due to the lack of adequate monument descriptions. Therefore, an elevation comparison summary for this report is only available along the NGS lines outside the well area. The first order level tie to line No. 101 (BMA-1208) was +3.37 millimeters in 17.21 kilometers. The allowable error of closure was 12.44 millimeters.
Date: October 1, 1984
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Consolidation of simulated nuclear metallic waste by vacuum coreless induction melting. (open access)

Consolidation of simulated nuclear metallic waste by vacuum coreless induction melting.

Vacuum coreless induction melting with bottom pouring has exceeded expectations for simplicity, reliability, and versatility when melting the zirconium and iron eutectic alloy. The melting tests have established that: the eutectic mixture of oxidized Zircaloy 4 hulls mixed with Type 316 stainless steel hulls can be melted at 41 kg/h at 40 kW with a power consumption of 1.03 kWh/kg and a melting temperature of 1260/sup 0/C; the life of a graphite crucible can be expected to be longer by a factor of 4 than was previously projected; the bottom-pour water-cooled copper freeze plug was 100% reliable; a 24-in.-tall stainless steel canister with 1/4-in.-thick walls (6-in. inside diameter) was satisfactory in every respect; an ingot formed from 4 consecutive heats poured into a stainless steel canister appeared to be approx. 99% dense after sectioning; preplaced scrap in the canister can be encapsulated with molten metal to about 99% density; large pieces of Zircaloy 4 and stainless steel scrap can be melted, but have differing melting parameters; the pouring nozzle requires further development to prevent solidified drops from forming at the hole exit after a pour. It is recommended that a large-scale cold mock-up facility be established to refine and test …
Date: October 1, 1984
Creator: Montgomery, D.R.
Object Type: Report
System: The UNT Digital Library
Geothermal feasibility study for Idaho State School and Hospital, Nampa, Idaho (open access)

Geothermal feasibility study for Idaho State School and Hospital, Nampa, Idaho

Apparently it is possible to obtain a geothermal source of water at about 3000 ft depth that should produce 500+ GPM at 160{sup 0}F. The present steam and condensate lines are poorly insulated which adds to the heating costs and, in addition, the condensate lines are in poor condition. If this system is retained, it will cost upwards of $100,000 to replace these condensate lines. This cost should be considered as an off-set against the cost of the geothermal system. This was not included in the economic analysis simply because the cost for these repairs is next to impossible to predict with any accuracy. Changing over to geothermal hot water system will reduce the gas consumption by 75%. Most of the remaining gas use (steam) would be in the laundry and kitchen. In preparing this study, the assumption was made that most buildings that are presently using hot water could be heated with 155{sup 0}F water. It is recommended that during the ensuing year the maintenance department be instructed to change the controls on several buildings to reduce the temperature of the hot water down to 155{sup 0}F to see if comfort can be maintained at the lower setting. When …
Date: October 1, 1984
Creator: Balzhiser, J.K.
Object Type: Report
System: The UNT Digital Library