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Valuation of Potash Occurrences Within the Nuclear Waste Isolation Pilot Plant Site in Southeastern New Mexico

Description: Report issued by the U.S. Bureau of Mines discussing potash occurrences of southeastern New Mexico. As stated in the introduction, "included in this report are discussions of the geology and geography of the study area, its potash mining history, and current and projected market conditions in the potash industry" (p. 2). This report includes maps, tables, and illustrations.
Date: 1980
Creator: Weisner, Robert C.; Lemons, Jim F., Jr. & Coppa, Luis V.
Partner: UNT Libraries Government Documents Department

MILS: The Mineral Industry Location System of the Federal Bureau of Mines

Description: Report issued by the U.S. Bureau of Mines discussing the Mineral Industry Location System (MILS), a mineral deposit data base. As stated in the abstract, "information on more than 135,000 mineral locations and processing plants in the United States is contained in the data base. This information includes the name, location, mineral commodity, type of operation, bibliography, and cross-reference for each property or prospect" (p. 1). This report includes maps, tables, and illustrations.
Date: 1980
Creator: Berg, Andrew W. & Carrillo, Fred V.
Partner: UNT Libraries Government Documents Department

Research and Innovation in the Building Regulatory Process

Description: Report issued by the U.S. National Bureau of Standards discussing studies conducted on building codes, standards, and regulations. The report includes transcripts from the 12th annual National Conference of States on Building Codes and Standards. This report includes tables, and illustrations.
Date: June 1980
Creator: Berry, Sandra A.
Partner: UNT Libraries Government Documents Department

Atlantic Coastal experiment III, FRV Delaware II cruise, 17-27 May 1977 and R/V ONRUST cruise, 28-30, June 1977. Data report

Description: The DELAWARE II and ONRUST cruises, continuations of Atlantic Coastal Experiment III, were made during May and late June, 1977, to compare seasonal changes in chlorophyll a, nitrogen nutrient, dissolved oxygen and phytoplankton composition within the mid-Atlantic and New York Bights. Data from 106 stations and 3300 km of surface mapping are reported as classical hydrographic listings, areal and/or vertical contours of chlorophyll a, inorganic nitrogen and salinity, and listings of phytoplankton species abun- dance. Temperature profiles from 100 stations are included, as well as res- piration experiments [ETS assay] for the dinoflagellate, Ceratium tripos.
Date: September 1, 1980
Creator: Malloy, S.; Stoddard, A. & von Bock, K. (eds.)
Partner: UNT Libraries Government Documents Department

ORECA CODE ASSESSMENT.

Description: Results of an assessment of the ORECA code are being presented. In particular it was found that in the case of loss of forced flow circulation the predicted peak core temperatures are very sensitive to the mean gas temperatures used in the evaluation of the pressure drop terms. Some potential shortcomings of the conduction algorithm for some specific applications are discussed. The results of these efforts have been taken into consideration in the current version of the ORECA code.
Date: July 1980
Creator: Kroeger, P. G.
Partner: UNT Libraries Government Documents Department

Field task proposal/agreement separation and purification of radioisotopes for research

Description: The present purpose of this program is to produce high-purity uranium-234 (99%) and polonium-209 for the scientific community, both Governmental and non-Governmental. In addition, facilities for separation and purification of protactinium-231, thorium-230, and thorium-229 are maintained in stand-by condition for the resumption of these processes when conditions warrant. The uranium-234 isotope is separated from aged plutonium-238 material, purified, and converted to solid U{sub 3}O{sub 8}. This oxide is subsequently shipped to Oak Ridge National Laboratory for distribution through their Isotope Sales Group. The principal use of uranium-234, which is recovered from aged plutonium-238, is in fission detectors used to monitor reactors. Approximately one-third of the total uranium in a fission detector is uranium-234. The other two-thirds is uranium-235. A typical detector might contain 15 mg total uranium. As the neutron flux in the reactor causes fission of the uranium-235 in the detector, it also converts the uranium-234 to uranium-235.
Date: November 20, 1980
Creator: Wilkes, W.R. & Eppley, R.E.
Partner: UNT Libraries Government Documents Department

Analysis of trapped gas in 1E34 detonators by gas chromatography

Description: A method was developed to extract and then analyze gas trapped in thermally aged 1E34 detonators. This gas was extracted into an evacuated volume and injected into a gas chromatograph for separation and quantitative analysis. To effect this gas extraction, a device was designed for puncturing the detonator cup and capturing the effused gas. Limited testing of five detonators in this device shows amounts of gas ranging from about 0.5 X 10 {sup -7} to 12 X 10 {sup - 7} moles.
Date: May 14, 1980
Creator: Warner, D.K.; Back, P.S. & Barnhart, B.V.
Partner: UNT Libraries Government Documents Department

LWRHU EB weld development

Description: Electron beam weld development studies were performed for both the platinum frit vent-to-vent cap weld and also the vent cap-to-body weld for the LWRHU Project using a Hamilton Standard EBW-6 Electron Beam Welder. A total of six (6) development welds each was performed to establish welding parameters and procedures which would produce satisfactory and acceptable welds. The relatively small size of the platinum frit vent dictated that the frit-to-vent cap weld would have to be limited as to depth of penetration and also to minimize the reduction of the porous frit areas.
Date: January 22, 1980
Creator: Greene, L.A.
Partner: UNT Libraries Government Documents Department

Quality program status report. January - March, 1980

Description: This report details activities in the Quality Control Program at Mound Laboratory during the reporting period of January through March 1980.
Date: April 18, 1980
Creator: Bohl, D.R.
Partner: UNT Libraries Government Documents Department

Finite-element calculations of near-field transient horizontal temperature and thermal stress distributions for the Climax granite nuclear spent-fuel-storage experiment

Description: Calculations of near-canister temperature and thermal stress fields in a horizontal plane through a typical spent nuclear fuel canister in the Climax granite experiment are presented, assuming homogeneity of the rock mass. The methodology is described. Three different canister spacings were investigated. The resulting temperature and stress plots show that a row of canisters may be satisfactorily approximated by a distributed plane source for points of interest which are at greater distances from the row than the canister spacing. Further, the thermal tensile stress changes are trivial and very much less than the calculated residual horizontal geostatic compressive stresses. A listing of the mesh-generator input is given for use in additional analyses.
Date: March 1, 1980
Creator: Greenlaw, R.C.
Partner: UNT Libraries Government Documents Department

TIGER -- A technology to improve the delivery capability of nuclear bombs and the survivability of the delivery aircraft

Description: The TIGER (Terminal guided and Extended-Range) Program was initiated in 1972 to study improved delivery capabilities for stockpiled tactical nuclear bombs. The Southeast Asia conflict fostered the development of air-delivered standoff conventional weapons utilizing terminal guidance systems. SNL initiated the TIGER program to determine if current nuclear bombs could be provided with a similarly accurate standoff capabilities. These conventional weapon delivery techniques, while allowing highly accurate attack, generally require entering the target area at high altitude to establish line of sight to the target. In parallel with the TIGER program, system studies analyzed this concept and showed marked improvement in aircraft and weapon survivability with moderate standoff (10--20 km) if low level deliveries (60 m) could be accomplished. As a result of this work, the TIGER program was redirected in early 1974 to demonstrate a standoff bomb with good accuracy (90 m CEP) when delivered from low flying aircraft. This program redirection resulted in the selection of an inertial guidance system to replace the earlier terminal guidance systems. This program was called the Extended-Range Bomb (ERB). In May 1974, a joint Air Force/DOE study identified the desirability of having a single tactical weapon which could be employed against either fixed, preselected targets, or mobile battlefield targets. Studies conducted on the ERB system showed that the inertially guided weapon could fly not only the standoff mission but also a return-to-target mission against the mobile battlefield targets whose locations are not known accurately enough to use a standoff delivery. The ERB program evolved from these initial investigations into an exploratory program to develop the hardware and demonstrate the technology required to fly standoff and return-to-target trajectories. The application of this technology in the form of field retrofit kits to the B61 bomb is called TIGER II.
Date: December 31, 1980
Partner: UNT Libraries Government Documents Department

In-situ tuff water migration/heater experiment: experimental plan

Description: Tuffs on the Nevada Test Site (NTS) are currently under investigation as a potential isolation medium for heat-producing nuclear wastes. The National Academy of Sciences has concurred in our identification of the potentially large water content ({le}40 vol %) of tuffs as one of the important issues affecting their suitability for a repository. This Experimental Plan describes an in-situ experiment intended as an initial assessment of water generation/migration in response to a thermal input. The experiment will be conducted in the Grouse Canyon Welded Tuff in Tunnel U12g (G-Tunnel) located in the north-central region of the NTS. While the Grouse Canyon Welded Tuff is not a potential repository medium, it has physical, thermal, and mechanical properties very similar to those tuffs currently under consideration and is accessible at depth (400 m below the surface) in an existing facility. Other goals of the experiment are to support computer-code and instrumentation development, and to measure in-situ thermal properties. The experimental array consists of a central electrical heater, 1.2 m long x 10.2 cm diameter, surrounded by three holes for measuring water-migration behavior, two holes for measuring temperature profiles, one hole for measuring thermally induced stress in the rock, and one hole perpendicular to the heater to measure displacement with a laser. This Experimental Plan describes the experimental objectives, the technical issues, the site, the experimental array, thermal and thermomechanical modeling results, the instrumentation, the data-acquisition system, posttest characterization, and the organizational details.
Date: August 1, 1980
Creator: Johnstone, J.K.
Partner: UNT Libraries Government Documents Department

Spent fuel handling and packaging program. Quarterly report, October-December 1979

Description: Balance of 13 fuel assemblies for the Climax programs were received; 9 were completely encapsulated, 4 were canistered without welding; all were placed in Hot Bay lag storage. Six Climax electrically heated mockup assemblies (EHMA) were pre-assembled at E-MAD, delivered to the Climax site and assembly was completed. The BWR fuel handling tool was fabricated and proof tested. The new constant air monitor (CAM) equipment was received. Fuel Temperature Test controller modifications were completed and testing was resumed. Calorimeter equipment installation was resumed; modification of lower vertical supports was completed; and the first review draft of the operating procedure was issued. The Lag Storage Pit ventilation test was completed.
Date: January 1, 1980
Creator: Durrill, D C
Partner: UNT Libraries Government Documents Department

Solar thermal repowering

Description: Solar central receiver technology is developing steadily with a promise of becoming a real commercial alternative for energy generation in the late 1980s. Significant potential markets have been identified, research and development of important components is proceeding well, and the first full-system verification experiment at Barstow, California, is under construction. However, much work still lies ahead. A big step toward the realization of large-scale commercial use of solar energy was taken when the Department of Energy (DOE) issued a solicitation in March 1979 for utility repowering/industrial retrofit system conceptual design studies employing solar central receivers. Twenty-two responses were evaluated, and twelve were selected for funding. The results of the twelve studies, plus one study completed earlier and one privately funded, are sufficiently encouraging to warrant proceeding to the next stage of the program: cost-shared projects chosen through open competition. Eight of he fourteen studies are for electric utility repowering of existing oil or natural gas generating plants. The other six are the first site-specific studies of the use of solar central receiver systems for industrial process heat. The industrial processes include gypsum board drying, oil refining, enhanced oil recovery, uranium ore processing, natural gas processing, and ammonia production. Site descriptions, project summaries, conceptual designs, and functional descriptions are given for each of these 14 studies.
Date: August 1, 1980
Partner: UNT Libraries Government Documents Department

Particle-beam fusion research facilities at Sandia National Laboratories

Description: Sandia research in inertial-confinement fusion (ICF) is based on pulse-power capabilities that grew out of earlier developments of intense relativistic electron-beam (e-beam) radiation sources for weapon effects studies. ICF involves irradiating a deuterium-tritium pellet with either laser light or particle beams until the center of the pellet is compressed and heated to the point of nuclear fusion. This publication focuses on the use of particle beams to achieve fusion, and on the various facilities that are used in support of the particle-beam fusion (PBF) program.
Date: December 31, 1980
Partner: UNT Libraries Government Documents Department

Assessment of effectiveness of geologic isolation systems. Geologic factors in the isolation of nuclear waste: evaluation of long-term geomorphic processes and catastrophic events

Description: SRI International has projected the rate, duration, and magnitude of geomorphic processes and events in the Southwest and Gulf Coast over the next million years. This information will be used by the Department of Energy`s Pacific Northwest Laboratory (PNL) as input to a computer model, which will be used to simulate possible release scenarios and the consequences of the release of nuclear waste from geologic containment. The estimates in this report, although based on best scientific judgment, are subject to considerable uncertainty. An evaluation of the Quaternary history of the two study areas revealed that each had undergone geomorphic change in the last one million years. Catastrophic events were evaluated in order to determine their significance to the simulation model. Given available data, catastrophic floods are not expected to occur in the two study areas. Catastrophic landslides may occur in the Southwest, but because the duration of the event is brief and the amount of material moved is small in comparison to regional denudation, such events need not be included in the simulation model. Ashfalls, however, could result in removal of vegetation from the landscape, thereby causing significant increases in erosion rates. Because the estimates developed during this study may not be applicable to specific sites, general equations were presented as a first step in refining the analysis. These equations identify the general relationships among the important variables and suggest those areas of concern for which further data are required. If the current model indicates that geomorphic processes (taken together with other geologic changes) may ultimately affect the geologic containment of nuclear waste, further research may be necessary to refine this analysis for application to specific sites.
Date: March 1980
Creator: Mara, S. J.
Partner: UNT Libraries Government Documents Department

GeoEnergy technology

Description: The goal of the GeoEnergy Technology Program is to improve the understanding and efficiency of energy extraction and conversion from geologic resources, hence maintaining domestic production capability of fossil energy resources and expanding the usage of geothermal energy. The GeoEnergy Technology Program conducts projects for the Department of Energy in four resource areas--coal, oil and gas, synthetic fuels and geothermal energy. These projects, which are conducted collaboratively with private industry and DOE`s Energy Technology Centers, draw heavily on expertise derived from the nuclear weapons engineering capabilities of Sandia. The primary technologies utilized in the program are instrumentation development and application, geotechnical engineering, drilling and well completions, and chemical and physical process research. Studies in all four resource areas are described.
Date: December 31, 1980
Partner: UNT Libraries Government Documents Department

Evaluation of tuff as a medium for a nuclear waste repository: interim status report on the properties of tuff

Description: This report is the second in a series of summary briefings to the National Academy of Science`s (NAS) Committee on Radioactive Waste Management dealing with feasibility of disposal of heat-producing radioactive waste in silicic tuff. The interim status of studies of tuff properties determined on samples obtained from Yucca Mountain and Rainier Mesa (G-tunnel) located on the Nevada Test Site (NTS) are discussed. In particular, progress is described on resolving issues identified during the first briefing to the NAS which include behavior of water in tuff when heated, the effect of the presence or absence of water and joints on the thermal/physical properties of tuff and the detailed/complex sorptive properties of highly altered and unaltered tuff. Initial correlations of thermal/physical and sorptive properties with the highly variable porosity and mineralogy are described. Three in-situ, at-depth field experiments, one nearly completed and two just getting underway are described. In particular, the current status of mineralogy and petrology, geochemistry, thermal and mechanical, radiation effects and water behavior studies are described. The goals and initial results of a Mine Design Working Group are discussed. Regional factors such as seismicity, volcanism and hydrology are not discussed.
Date: July 1, 1980
Creator: Johnstone, J.K. & Wolfsberg, K. (eds.)
Partner: UNT Libraries Government Documents Department

Analysis of thermal data from drill holes UE25a-3 and UE25a-1, Calico Hills and Yucca Mountain, Nevada Test Site

Description: Thermal data from two sites about 20 km apart in the Nevada Test Site indicate that heat flow both within and below the upper 800 meters is affected significantly by hydrothermal convection. For hole UE25a-1, Yucca Mountain, the apparent heat flow above the water table ({similar_to}470 m) is 54 mWm{sup -2} ({similar_to}1.3 HFU). Below the water table, the temperature profile indicates both upward and downward water movement within the hole and possibly within the formation. Hole UE25a-3, Calico Mountain, is characterized by conductive heat flux averaging 135 mWm{sup -2} ({similar_to}3.2 HFU) to a depth of about 700 meters below which water appears to be moving downward at the rate of nearly 1 ft y{sup -1} (255 mm y{sup -1}). Between 735 and 750 meters, the hole intersected a nearly vertical fault along which water seems to be moving vertically downward. The nearly threefold variation in conductive heat flow over a lateral distance of only 20 km suggests the presence of a more deeply seated hydrothremal convective system with a net upward flow beneath Calico Hills and a net downward flow beneath Yucca Mountain.
Date: August 12, 1980
Creator: Sass, J. H.; Lachenbruch, A. H. & Mase, C. W.
Partner: UNT Libraries Government Documents Department

Spent fuel dry storage technology development: thermal evaluation of isolated drywells containing spent fuel (1 kW PWR spent fuel assembly)

Description: A spent fuel Isolated Drywell Test was conducted at the Engine-Maintenance, Assembly and Disassembly (E-MAD) facility on the Nevada Test Site. Two PWR spent fuel assemblies having a decay heat level of approximately 1.1 kW were encapsulated inside the E-MAD Hot Bay and placed in instrumented near-surface drywell storage cells. Temperatures from the two isolated drywells and the adjacent soil have been recorded throughout the 19 month Isolated Drywell Test. Canister and drywell liner temperatures reached their peak values (254{sup 0}F and 203{sup 0}F, respectively) during August 1979. Thereafter, all temperatures decreased and showed a cycling pattern which responded to seasonal atmospheric temperature changes. A computer model was utilized to predict the thermal response of the drywell. Computer predictions of the drywell temperatures and the temperatures of the surrounding soil are presented and show good agreement with the test data.
Date: September 1, 1980
Creator: Unterzuber, R & Wright, J B
Partner: UNT Libraries Government Documents Department

Spent fuel dry storage technology development: thermal evaluation of sealed storage cask containing spent fuel

Description: A PWR spent fuel assembly was encapsulated inside the E-MAD Hot Bay and placed in a instrumented above surface storage cell during December 1978 for thermal testing. Instrumentation provided to measure canister, liner and concrete temperatures consisted of thermocouples which were inserted into tubes on the outside of the canister and liner and in three radial positions in the concrete. Temperatures from the SSC test assembly have been recorded throughout the past 16 months. Canister and liner temperatures have reached their peak values of 200{sup 0}F and 140{sup 0}F, respectively. Computer predictions of the transient and steady-state temperatures show good agreement with the test data.
Date: August 1, 1980
Creator: Schmitten, P.F. & Wright, J.B.
Partner: UNT Libraries Government Documents Department

Program Plan: field radionuclide migration studies in Climax granite

Description: This Program Plan describes the field radionuclide migration studies we plan to conduct in the Climax granite at the Nevada Test Site. Laboratory support studies are included to help us understand the geochemical and hydrologic processes involved in the field. The Program Plan begins with background information (Section 1) on how this program fits into the National Waste Terminal Storage Program Plan and discusses the needs for field studies of this type. The objectives stated in Section 2 are in direct response to these needs, particularly the need to determine whether laboratory studies accurately reflect actual field conditions and the need for field testing to provide a data base for verification of hydrologic and mass transport models. The technical scope (Section 3) provides a work breakdown structure that integrates the various activities and establishes a base for the technical approach described in Section 4. Our approach combines an interactive system of field and laboratory migration experiments with the use of hydrologic models for pre-test predictions and data interpretation. Section 5 on program interfaces identifies how information will be transferred to other related DOE projects. A schedule of activities and major milestones (Section 6) and the budget necessary to meet the project objectives (Section 7) are included in the Program Plan. Sections 8 and 9 contain brief descriptions of how the technical and program controls will be established and maintained and an outline of our quality assurance program. This program plan is an initial planning document and provides a general description of activities. An Engineering Test Plan containing detailed experimental test plans, an instrumentation plan and equipment design drawings will be published as a separate document.
Date: November 1, 1980
Creator: Isherwood, D.; Raber, E.; Coles, D. & Stone, R.
Partner: UNT Libraries Government Documents Department

Commercial waste and spent fuel packaging program. Quarterly report, July through September 1980

Description: This document is a report of activities performed by Westinghouse Advanced Energy Systems Division-Nevada Operations at the E-MAD Facility, Area 25, Nevada Test Site, in meeting subtask objectives during the fourth quarter of Fiscal Year 1980. These activities include removal of the one kilowatt (kw) spent fuel assembly and installation of a two kw assembly into the Fuel Temperature Test in the West Process Cell; transfer of fueled canisters to Drywells 1, 2 and 3, and initiation of the Drywell Interaction Test; initiation of the two kw Drywell Test in Drywell 5; calorimetry; gas sampling; neutron spectra measurement; installation and qualification of the Canister Cutter; and continuation of the three kw Soil Temperature Test.
Date: October 1, 1980
Creator: Hakl, A R
Partner: UNT Libraries Government Documents Department