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Selection of Data Entry Equipment

Description: Report issued by the U.S. National Bureau of Standards discussing information on data entry equipment selection by Federal agencies and organizations. As stated in the abstract, "this report provides information about economic and general operational considerations, steps to be followed in acquisition and training, and other factors pertinent to data entry equipment selection" (p. iii). This report includes a table.
Date: November 1979
Creator: Recicar, Steve A.
Partner: UNT Libraries Government Documents Department

Construction of a Large Transverse Electromagnetic Cell

Description: Report issued by the U.S. National Bureau of Standards discussing the construction of large electromagnetic cells. As stated in the introduction, "this instruction provides information and procedures necessary to fabricate a large transverse electromagnetic (TEM) cell to be used for experimental "electromagnetic interference" (EMI) evaluation studies" (p. 1). This report includes illustrations, and photographs.
Date: February 1979
Creator: Decker, W. F. & Wilson, W. A.
Partner: UNT Libraries Government Documents Department

Preliminary calculations related to the accident at Three Mile Island

Description: This report discusses preliminary studies of the Three Mile Island Unit 2 (TMI-2) accident based on available methods and data. The work reported includes: (1) a TRAC base case calculation out to 3 hours into the accident sequence; (2) TRAC parametric calculations, these are the same as the base case except for a single hypothetical change in the system conditions, such as assuming the high pressure injection (HPI) system operated as designed rather than as in the accident; (3) fuel rod cladding failure, cladding oxidation due to zirconium metal-steam reactions, hydrogen release due to cladding oxidation, cladding ballooning, cladding embrittlement, and subsequent cladding breakup estimates based on TRAC calculated cladding temperatures and system pressures. Some conclusions of this work are: the TRAC base case accident calculation agrees very well with known system conditions to nearly 3 hours into the accident; the parametric calculations indicate that, loss-of-core cooling was most influenced by the throttling of High-Pressure Injection (HPI) flows, given the accident initiating events and the pressurizer electromagnetic-operated valve (EMOV) failing to close as designed; failure of nearly all the rods and gaseous fission product gas release from the failed rods is predicted to have occurred at about 2 hours and 30 minutes; cladding oxidation (zirconium-steam reaction) up to 3 hours resulted in the production of approximately 40 kilograms of hydrogen.
Date: August 1, 1979
Creator: Kirchner, W.L. & Stevenson, M.G.
Partner: UNT Libraries Government Documents Department

Tester status report: April-June 1979

Description: This report details tester status and activities in support of testing of timers, actuators, detonators, firing sets, transducers, isolators, and pyrospacers for the period of April through June 1979.
Date: August 31, 1979
Creator: Draut, C.F.
Partner: UNT Libraries Government Documents Department

Mound Facility. 1978 annual report

Description: For Mound Facility, the year 1978 was one of progress marked by enhanced mission assignments and significant milestones. The thirtieth anniversary of the site was celebrated, and Monsanto Research Corporation began a new 5 year contract to operate the Mound Facility. Long-standing production assignments were strengthened, and were were given a new responsibility: to develop and produce all ceramic parts used in Mound-build products. progress toward US energy objectives was bolstered by Mound programs supporting the development of nuclear fusion poser, unlocking previously us attainable fossil fuels, ensuring the safety and security of nuclear material handling operations, and exploring the real promise of energy form the sun. In 1978, we focused our attention on many efforts aimed at a brighter, more secure future.
Date: December 31, 1979
Partner: UNT Libraries Government Documents Department

Tester status report: October-December 1978

Description: This report details the status of the testers which provide the testing support of timers, actuators, detonators, firing sets, transducers, isolators, and pyrospacers during the time period of October through December 1978.
Date: February 9, 1979
Creator: Draut, C.F.
Partner: UNT Libraries Government Documents Department

LWRHU GTA Weld Development

Description: Nineteen LWRHU Development Welds have been made. Welds WD-1 through WD-4 were made early in the program to obtain preliminary joint design data. Welds WD-5 through WD-10 were made with the vertical leg of the shim located toward the closure end cap. A decision was made to locate the shim with the vertical leg on the fuel side of the capsule; therefore, the data obtained on the above capsule welds will not be included in this report. A tantalum pellet machined to the configuration of the fuel pellet was placed inside each development capsule. O.D. shrinkage measurements were taken across the stand-off ring nearest the weld. A small increase in capsule length resulted from the weld bead on the end of the capsule.
Date: December 13, 1979
Creator: Burgan, C.E.
Partner: UNT Libraries Government Documents Department

MAD-1021 slapper fabrication, LASL P.O. CM8-2909G-1

Description: One hundred MAD-1021 slapper test devices were built to fill the reimbursable order CM8-2909G-1 for W.F. Hemsing of Los Alamos Scientific Laboratory. Physical vapor deposition (PVD) techniques were successfully used to prepare the slapper foil assemblies. The 0. 381 mm square bridge foils were of aluminium 3 micrometers thick. Copper solder pads of 1.0 to 1.5 micrometer thickness were also applied using PVD techniques. A total of 120 were fabricated and submitted to the fabrication group for assembly. The 100 completed slapper units were fabricated with 0.025 mm thick Kapton flyers. Barrels for these slapper units were 0.38 mm long with a 0.42 mm diameter.
Date: January 29, 1979
Creator: Nesslage, G.V. & VanKlompenberg, R.A.
Partner: UNT Libraries Government Documents Department

Applicability of microautoradiography to sorption studies

Description: The technique of microautoradiography was applied to the study of the sorption of uranium and americium on five rock types which exist at the Nevada Test Site. It was found that autoradiograms could be prepared in a few days which would allow the specific minerals responsible for sorption to be identified. Furthermore, the state of aggregation of the sorbed species was clearly indicated. It was concluded that microautoradiography was a useful adjunct to currently used methods for studying sorption of certain radionuclides.
Date: January 1, 1979
Creator: Thompson, J. L. & Wolfsberg, K.
Partner: UNT Libraries Government Documents Department

Petrology of tuff units from the J-13 drill site, Jackass Flats, Nevada

Description: The J-13 drill hole, located in Jackass Flats, Nevada Test Site, has penetrated 125 m of alluvium and 932 m of tuff. Most of the tuff deposits consist of welded tuffs; glass phases in the tuffs have been replaced by authigenic minerals, mainly K-feldspar, silica, and zeolites. The zonation of authigenic minerals, with depth, indictes that alteration of glass phases and filling of vugs occurred during welding and compaction of tuff units soon after deposition and by interaction with groundwater. Zonation of authigenic minerals in tuff deposits at Jackass Flats is similar to mineral zonation in tuffs elsewhere at the Nevada Test Site and in tuff deposits of west Texas. All appear to have been developed by leaching of glass phases and deposition of authigenic minerals in open hydrologic systems. 10 figures, 38 tables.
Date: December 31, 1979
Creator: Heiken, G.H. & Bevier, M.L.
Partner: UNT Libraries Government Documents Department

Sandia Laboratories radiation facilities. Second edition

Description: This brochure is designed as a basic source of information for prospective users of Sandia Laboratories Radiation Facilities. It contains a brief description of the various major radiation sources, a summary of their output characteristics, and additional information useful to experimenters. Radiation source development and source upgrading is an ongoing program, with new source configurations and modes of operation continually being devised to satisfy the ever-changing radiation requirements of the users. For most cases, the information presented here should allow a potential user to assess the applicability of a particular radiation facility to a proposed experiment and to permit some preirradiation calculations and planning.
Date: July 1, 1979
Creator: Choate, L.M. & Schmidt, T.R.
Partner: UNT Libraries Government Documents Department

Preliminary evaluation of the radioactive waste isolation potential of the alluvium-filled valleys of the Great Basin

Description: The occurrences, geologic features, hydrology, and thermal, mechanical, and mineralogical properties of the alluvium-filled valleys are compared with those of other media within the Great Basin. Computer modeling of heat conduction indicates that heat generated by the radioactive waste can be dissipated through the alluvium in a manner that will not threaten the integrity of the repository, although waste emplacement densities will be lower than for other media available. This investigation has not revealed any failure mechanism by which one can rule out alluvium as a primary waste isolation medium. However, the alluvium appears to rank behind one or more other possible media in all properties examined except, perhaps, in sorption properties. It is therefore recommended that alluvium be considered as a secondary isolation medium unless primary sites in other rock types in the Great Basin are eliminated from consideration on grounds other than those considered here.
Date: August 1, 1979
Creator: Smyth, J.R.; Crowe, B.M.; Halleck, P.M. & Reed, A.W.
Partner: UNT Libraries Government Documents Department

Aerial Radiometric and Magnetic Reconnaissance Survey of Portions of Arizona, Idaho, Montana, New Mexico, South Dakota and Washington: Final Report, Volume 1. Instrumentation and Methods

Description: From abstract: The objective of the work was to define areas showing surface indications of a generally higher uranium content where detailed exploration for uranium would most likely be successful.
Date: March 1979
Creator: Texas Instruments Incorporated
Partner: UNT Libraries Government Documents Department

Mineralogy and petrology of tuff units from a UE25a-1 drill site, Yucca Mountain, Nevada

Description: Drill hole UE25a-1 has penetrated tuffs of Tertiary age which contain two major zeolitized horizons at depths below 380 m. These horizons are restricted to low-density, high-porosity nonwelded tuffs below the basal vitrophyre of the Topopah Springs Member of the Paintbrush Tuff (approximately 70 m above the current water table), and interfinger with more-densely-welded devitrified tuffs of granophyric mineralogy. Zeolites occur as glass pyroclast replacement, vug linings, and fracture fillings. Nonwelded units above the welded portion of the Topopah Springs Member are essentially unaltered, indicating that they have never been ground water-saturated for any significant length of time. Zeolite mineral assemblages appear to be characteristic of low temperature (<100{sup 0}C) ground water alteration of glass in an open hydrologic system. The principal zeolite phase is high-Si clinoptilolite with Si/Al ratios of 4.7 to 6.0. Ca tends to be the dominant large-radius cation, but grains with dominant K or Na are not uncommon, particularly with increasing depth. Compositional variations in clinoptilolite may be due to ground water composition or original pyroclast composition. Minor amounts of mordenite, characterized by lower silica content (<55 wt %) and high alkali content (>10 wt % Na{sub 2}O + K{sub 2}O), occur as vug fillings at depths below 500 m. Presence of mordenite may indicate slightly elevated alteration temperatures, but more likely reflects enrichment of ground water in alkalis with depth. Mineralogical, compositional, and textural similarities of the zeolitized tuffs from UE25a-1 and J-13 are compatible with a single episode of crystallization. 16 figures.
Date: November 1, 1979
Creator: Sykes, M.L.; Heiken, G.H. & Smyth, J.R.
Partner: UNT Libraries Government Documents Department

Sorption--desorption studies on argillite. I. Initial studies of strontium, technetium, cesium, barium, cerium, and europium

Description: Distribution ratios were determined for sorption--desorption of radioactive tracers between Eleana argillite available from the Nevada Test Site and a water prepared to be representative of the natural groundwater composition. The measurements were preformed at 22{sup 0}C and 70{sup 0}C under atmospheric oxygen conditions. The order of increasing distribution coefficient by element at both temperatures is Tc(VII), Sr, Cs, Ba, Eu, and Ce. The effects of surface area and mineralogy were also investigated. 34 figures, 26 tables.
Date: March 1, 1979
Creator: Erdal, B.R.; Aguilar, R.D.; Bayhurst, B.P.; Oliver, P.Q. & Wolfsberg, K.
Partner: UNT Libraries Government Documents Department

Technical concept for rock mechanics tests, Climax Granite, NTS

Description: If we are to believe our predictions of the thermomechanical behavior of the material surrounding a nuclear waste repository in granite, we must test the computational methods used in making the predictions. If thermal loadings appropriate to a real repository are used, thermally induced displacements and strains are quite small, and available geotechnical instrumentation is only marginally able to measure these effects to the accuracy desired to make thorough tests of the predictions. We outline a three-step program to address these issues. (1) Conduct experiments in which the thermal loading is large compared to that induced by a real repository. This will permit us to make accurate measurements with available instrumentation. (2) Simultaneously, develop improved instrumentation that will enable us to make accurate measurements of motions induced by thermal loadings appropriate to a real repository. (3) Finally, conduct a second set of experiments, with the improved instrumentation and thermal loading similar to that of a real repository in granite. If we can predict the effects of this thermal loading to a few percent over distances of tens of meters for time periods of a few years, and demonstrate that these predictions are correct, we can have reasonable confidence that, using the same methods, we can predict the behavior over thousands of meters for hundreds of years to an order of magnitude. That accuracy should be satisfactory for those distances and times.
Date: February 1, 1979
Creator: Hearst, J.R.
Partner: UNT Libraries Government Documents Department

Waste-isolation projects, FY 1978

Description: This report describes Lawrence Livermore Laboratory (LLL) activities during FY 1978 in support of the National Waste Terminal Storage Program. Current projects at LLL fall into three categories: (1) field testing, (2) laboratory rock mechanics measurements, and (3) laboratory studies of sorption and leaching. Field test activities conducted in the Climax granite at the Nevada Test Site included electrical heater tests, preparation for a spent-fuel-storage test, and planning for a series of rock mechanics tests. The heater tests determined the in situ thermal properties of Climax granite and its in situ permeability as a function of rock temperature. The two main laboratory rock mechanics projects involved (1) measurement of the permeability, electrical conductivity, and acoustic velocity of 15-cm-diam cores of granitic rocks over a range of confining pressure, pore (water) pressure, and deviatoric stress, and (2) measurement of rock thermal properties as a function of temperature and confining pressure in the presence of pore fluids to 770{sup 0}K and 200 Mpa. The leaching studies made use of an LLL-designed, single-pass leaching apparatus with three solutions, two leach temperatures, and three flow rates. The material evaluated was Np--Pu-doped simulated waste glass from Battelle Pacific Northwest Laboratories. The sorption studies involved standard static measurements of the equilibrium distribution coefficient (K/sub d/) for various radionuclides on a variety of rocks, and flow-through-core studies of dynamic sorption.
Date: January 12, 1979
Creator: Ramspott, L.D. (ed.)
Partner: UNT Libraries Government Documents Department

Sorption--desorption studies on tuff. I. Initial studies with samples from the J-13 drill site, Jackass Flats, Nevada

Description: Distribution coefficients were determined for sorption--desorption of radionuclides between each of three different types of tuff from drill hole J-13 at the Nevada Test Site and water from that well. The measurements were performed under atmospheric conditions at 22{sup 0}C and 70{sup 0}C. Sorption ratios vary greatly with lithologic variety of tuff. A tuff high in zeolite minerals has high sorption ratios (in decreasing order) for Eu, Ba, Cs, and Am and intermediate ratios for Sr and Pu. A tuff high in glass shows very high ratios for Ba, Sr, and Cs, intermediate values for Am and Pu, and low values for Ce and Eu. A devitrified tuff similar mineralogically to a microgranite exhibits intermediate values for Ba, Cs, Am, and Pu and low values for Eu, Ce, and Sr. Values for Ru are low, and those for Mo, Sb, and I are very low or zero for the three types. 34 figures, 32 tables.
Date: April 1, 1979
Creator: Wolfsberg, K.; Bayhurst, B.P.; Crowe, B.M.; Daniels, W.R.; Erdal, B.R.; Lawrence, F.O. et al.
Partner: UNT Libraries Government Documents Department

NTS Terminal Waste Storage Project. Annual report, FY 1978 (should have been 1979)

Description: The primary thrust of the NTS Terminal Waste Storage Project during FY 1978 was to continue an evaluation of the suitability of the Nevada Test Site (NTS) for siting a commercial spent fuel or high-level waste repository. At the beginning of the year, three primary issues were identified. They are: (1) is waste isolation at the NTS compatible with weapons testing; (2) are there suitable geohydrologic settings available on the NTS; and (3) are there suitable disposal media available at NTS. The NTS Terminal Waste Storage Project has been organized primarily to address these three issues. The southwestern area of the NTS has been identified as compatible with both current and future weapons testing. The NTS and adjacent areas of southern Nevada contain media which are probably suitable for waste isolation and which occur in a region characterized by long groundwater flow paths through sorptive media. However, utilization of the southwestern part of NTS requires that several geotechnical issues be addressed intensively. These are: (1) the potential for earthquakes at and near NTS; (2) the potential for future volcanism at possible repository sites; (3) the location and nature of faults; and (4) the characterization of the groundwater flow system from possible repository sites to places of discharge. Four potential disposal media available on the NTS were studied during FY 1978. Studies of one of these media, alluvium, were suspended due to the low near-field thermal conductivity. Studies of other potential media, granite, argillite, and tuff, will continue during FY 1979 since it appears that these media could be used for emplacement of commercial spent fuel or high-level waste. Geologic site investigations have and will continue to evaluate areas with these media.
Date: December 31, 1979
Partner: UNT Libraries Government Documents Department

Instrument selection, installation, and analysis of data for the spent fuel mine-by, Nevada Test Site, Climax Stock

Description: During the time period of February to April, 1979, twelve rod extensometers and twenty-two convergence measurement points were installed, calibrated and monitored in support of the spent fuel mine in granite. Readings taken during heading and bench advance shows good instrument stability, with little or no anchor creep or slippage. Repeat calibrations indicate excellent repeatability. Measurement points within the heater drifts indicate little closure. Convergence pins within the spent fuel drift were subjected to significant blast damage that resulted in a discontinuous record. A numerical analysis of the stresses and displacements of the rock mass as a result of the mine-by was performed. Two methods, finite element and displacement discontinuity, were used to model the mine-by. Comparison of the actual to predicted displacements show good agreement for the 33{sup 0} and 50{sup 0} extensometers for a rock mass modulus of 3 to 5 x 10{sup 6} psi and Poisson`s ratio of .2. The horizontal extensometers however indicate a convergence of anchor and collar (divergence predicted) and the IRAD stressmeters installed within the pillar indicate a significant reduction in vertical compression during mining of the heading. A simple reduction of pillar modulus will not account for the observed stress and displacement changes. Varying the ratio of vertical to horizontal stress ratio over the range .8 to 1.25 also did not account for observed stresses and displacements. It is concluded that the displacements and stresses are a result of block motion or joint slippage within the pillars. This is primarily the result of the small dimensions of the pillars in relation to the spent fuel and heater drifts. This joint slippage can account for the formation of a stable stress arch around the openings and thus a relaxation of the pillar.
Date: July 1, 1979
Creator: Schrauf, T. & Board, M.
Partner: UNT Libraries Government Documents Department

Measurement Assurance for Gage Blocks

Description: Report discussing the philosophy of measurement assurance and the three levels of measurement assurance programs. The measurement assurance programs are outlined to show how control over the measurement process can be maintained and how the offset (or systematic error) from the unit of length maintained by the National Bureau of Standards ban be made negligible. This monograph is intended for those who need to know on a continuing basis the uncertainty of their gage block calibration procedure.
Date: February 1979
Creator: Croarkin, Carroll; Beers, John & Tucker, Clyde
Partner: UNT Libraries Government Documents Department