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Guideline on Major Job Accounting Systems: The System Management Facilities (SMF) for IBM Systems Under OS/MVT

Description: Report issued by the U.S. National Bureau of Standards discussing the System Management Facilities for IBM systems. As stated in the introduction, "the purpose of SMF, as stated in the IBM manual, is to provide the means for gathering and recording information that can be used for billing customers or evaluating system usage" (p. 1). This report includes tables, and illustrations.
Date: October 1978
Creator: Durbin, Gary; Kinney, Todd; Lamasney, Peter; Newman, Edward & Syrett, Edward
Partner: UNT Libraries Government Documents Department

Tentative Provisions for the Development of Seismic Regulations for Buildings: A Cooperative Effort with the Design Professions, Building Code Interests, and the Research Community

Description: Report issued by the U.S. National Bureau of Standards discussing building codes and standards in earthquake-prone areas. As stated in the introduction, "the basic purpose of this project is to present, in one comprehensive document, current state-of-knowledge in the fields of engineering seismology and engineering practice as it pertains to seismic design and construction of buildings" (p. 1). This report includes tables, and illustrations.
Date: June 1978
Creator: Applied Technology Council
Partner: UNT Libraries Government Documents Department

CORES Operations Manual: Bureau of Mines Core Repository System

Description: Report issued by the U.S. Bureau of Mines discussing the CORES operations manual. As stated in the abstract, "this report describes the new Bureau of Mines Core Repository System (CORES) and presents the methods for selecting, processing, and storing physical samples and descriptive data for future reference by earth scientists" (p. 1). This report includes tables, illustrations, and photographs.
Date: 1978
Creator: United States. Bureau of Mines.
Partner: UNT Libraries Government Documents Department

Microfilming Maps of Abandoned Anthracite Mines: Mines in the Southern Anthracite Field

Description: Report issued by the U.S. Bureau of Mines discussing the microfilming of abandoned anthracite mine maps in Pennsylvania. As stated in the abstract, "a catalog of the microfilmed maps of 47 of 49 major mines and 18 independent mines in the Southern field is presented" (p. 1). This report includes maps, tables, and illustrations.
Date: 1978
Creator: Gait, G. B.
Partner: UNT Libraries Government Documents Department

Environmental monitoring summary: 1977

Description: Monsanto Research Corporation operates Mound Facility, a government-owned facility of the U.S. Department of Energy (DOE) in Miamisburg, Ohio. Mound Facility is an integrated research, development, and production facility performing work in support of DOE weapon and nonweapon programs with emphasis on explosive and nuclear technology. This report provides information on the environmental monitoring of the Mound plant for 1977.
Date: June 9, 1978
Partner: UNT Libraries Government Documents Department

An introduction to Mound Facility

Description: This report discusses various aspects of the Mound Laboratory including; who they are, what they do, their technological capabilities, and their resources.
Date: April 1, 1978
Partner: UNT Libraries Government Documents Department

NTS terminal waste storage. Monthly technical status report

Description: The interim draft report containing the first stage of CSC`s work on prediction of subsurface ground motion was completed. Twenty-four stations of the seismic monitoring network are now operational. The location for the first exploratory hole in Calico Hills was changed based on interpretation of magnetic and electrical geophysical data. Two core holes were completed in the Climax Stock in the Pile Driver tunnel complex. Drilling on the first exploratory hole at Yucca Mountain commenced on July 30, 1978. Field reconnaissance of granitic rocks in southern Nevada continued, including locations in Esmeralda, Nye, and White Pine Counties. The modeling of the Eleana Heater Experiment showed good agreement with field temperature data for conduction energy transfer. A rough draft of the tuff scoping report was completed. Review of the LASL quality program plan for their activities on the NTS Terminal Waste Storage Program was completed by Sandia Quality Assurance. A geological reconnaissance of the region near the Yucca Mountain drill site suggested a high probability that large, reasonably unfaulted blocks of tuff exist in the area.
Date: July 31, 1978
Partner: UNT Libraries Government Documents Department

Preliminary evaluation of 30 potential granitic rock sites for a radioactive waste storage facility in southern Nevada

Description: Results of preliminary study are presented which was performed under subtask 2.7 of the NTS Terminal Waste Storage Program Plan for 1978. Subtask 2.7 examines the feasibility of locating a nuclear waste repository in a granitic stock or pluton in southern Nevada near the Nevada Test Site (NTS). It is assumed for the purposes of this study that such a repository cannot be located at NTS. This assumption may or may not be correct. This preliminary report does not identify a particular site as being a suitable location for a repository. Nor does it absolutely eliminate a particular site from further consideration. It does, however, answer the basic question of probable suitability of some of the sites and present a systematic method for site evaluation. Since the findings of this initial study have been favorable, it will be followed by more exhaustive and detailed studies of the original 30 sites and perhaps others. In future studies some of the evaluation criteria used in the preliminary study may be modified or eliminated, and new criteria may be introduced.
Date: February 15, 1978
Creator: Boardman, C.R. & Knutson, C.F.
Partner: UNT Libraries Government Documents Department

Waste isolation projects, FY 1977

Description: The technology and data base required to license a nuclear repository in a crystalline rock medium, located at or near the Nevada Test Site are being developed. The program consists of three related project areas: field and laboratory studies of the availability and migration of radionuclides in ground water; thermomechanical response of granite, through heater tests at the Climax stock of the Nevada Test Site; and laboratory measurements of physical properties of rocks at elevated temperatures and pressures, including physical/chemical factors that inhibit water transport in deep silicate rocks. Work accomplished in these areas is report. (LK)
Date: January 18, 1978
Creator: Ramspott, L.D. (ed.)
Partner: UNT Libraries Government Documents Department

Measuring the permeability of Eleana argillite from area 17, Nevada Test Site, using the transient method

Description: Using the transient method, we determine the permeability of high-quartz Eleana argillite from the Nevada Test Site as a function of effective pressure. By comparing calculated and observed pressure decay in the upstream reservoir, we have determined the permeability of intact and fractured specimens at effective pressures ranging from 1.0 to 24.0 MPa. Over this pressure range, Eleana argillite has a low permeability (10{sup -16} to 10{sup -19} cm{sup 2}) when intact and a higher permeability (10{sup -12} to 10{sup -17} cm{sup 2}) with one induced through-going fracture.
Date: December 11, 1978
Creator: Lin, W.
Partner: UNT Libraries Government Documents Department

Flexible armored blanket development

Description: An exploratory development contract was undertaken on December 23, 1977 which had as its purpose the development and demonstration of a flexible armored blanket design suitable for providing ballistic protection to nuclear weapons during shipment. Objectives were to design and fabricate a prototype blanket which will conform to the weapon shape, is troop-handleable in the field, and which, singly or in multiple layers, can defeat a range of kinetic energy armor piercing (AP) ammunition potentially capable of damaging the critical portion of the nuclear weapon. Following empirical testing, including the firing of threat ammunition under controlled laboratory and field test conditions, materials were selected and assembled into two blanket designs, each weighing approximately 54 kg/m{sup 2} (11 lbs/ft{sup 2}) and estimated to cost from $111 to $180 per ft{sup 2} in production. A firing demonstration to evidence blanket performance against terrorist/light infantry weapons, heavy infantry weapons, and aircraft cannon was conducted for representatives of the DOD and interested Sandia employees on April 12, 1978. The blankets performed better than anticipated defeating bullets up to 7.62 mm x 51 mm AP with one layer and projectiles up to 23 mm HEI with two layers. Based on these preliminary tests it is recommended that development work be continued with the following objectives: (1) the selection by the DOD of priority applications, (2) the specific design and fabrication of sufficient quantities of armored blankets for field testing, (3) the evaluation of the blankets by DOD operational units, with reports to Sandia Laboratories to enable final design.
Date: May 1, 1978
Creator: Roth, E.S.
Partner: UNT Libraries Government Documents Department

Head-end reprocessing studies with H.B. Robinson-2 fuel

Description: A series of exploratory hot-cell tests was made to determine the effects of voloxidation on tritium, fission product removal, and on subsequent steps of the light water reactor fuel cycle. The 100-g scale experiments indicated that >99% of the tritium, 50% of the {sup 14}C, 6% of the {sup 85}Kr, and smaller amounts of other elements were volatilized and collected when the UO{sub 2} was roasted in air at 480{sup 0}C for {similar_to} h. There was little effect on the solubility of the uranium and plutonium in HNO{sub 3}. The experiments indicated that the first 2-h leach usually dissolved >99.9% of the uranium and plutonium, and varying amounts of fission products, in voloxidized or unvoloxidized fuel. Two additional HNO{sub 3} leaches on the unvoloxidized fuel dissolved all but 0.004% of the plutonium; the additional leaches on the voloxidized material left {similar_to}.02% of the plutonium. (28 figs., 21 tables)
Date: June 1, 1978
Creator: Goode, J.H. & Stacy, R.G.
Partner: UNT Libraries Government Documents Department

AFCT/TFCT/ISFS Program. Technical progress report, July 1, 1978-September 30, 1978

Description: This is the last in a series of quarterly progress reports on research and development studies performed for the Alternate Fuel Cycle Technologies/Thorium Fuel Cycle Technologies/International Spent Fuel Receipt and Storage (AFCT/TFCT/ISFS) Program. This program provided information needed by industry to close the back end of the power reactor fuel cycle. During the last quarter. studies were conducted on the following task: Thorium Resource Price Analyses; Investigation of Air Cleaning Processes for Removing Tributyl Phosphate from Off-Gas Streams; Study of Iodine Chemistry in Process Solutions; High-Level Waste Treatment; Electropolishing to Decontaminate Metallic Waste from Alternate and Thorium Converter Fuel Cycles; US Scale Transport, Dispersion and Removal Model Comparison; Safety Criticality Experiments; and Criticality Research in Support of Thorium Fuel Cycle Technology Program.
Date: September 1978
Creator: Hill, O. F.
Partner: UNT Libraries Government Documents Department

Criticality research in support of chemical reprocessing in the Thorium Fuel Cycle Technology Program: basic process description

Description: The basis processes for reprocessing thorium based light water reactor type fuels are defined for use in identifying criticality data needs. The Reference Thorium Fuel Cycle is used as the primary fuel cycle. Material forms and compositions are described for each major processing step. These forms consist of nitrates and oxides of Th--U--Pu combinations. Fuel fabrication and fuel pool storage facilities are also defined to the extent they interact with fuel reprocessing.
Date: May 1978
Creator: Libby, R. A.
Partner: UNT Libraries Government Documents Department

Alternate Fuel Cycle Technologies/Thorium Fuel Cycle Technology Programs. Quarterly report for period 1 April--30 June 1978

Description: Voloxidation and dissolution studies: rotary-kiln heat-transfer tests are under way using a small rotary kiln along with the development of a mathematical model to determine kiln-heat-flux profiles necessary to maintain a desired temperature gradient. The erosion/corrosion test for evaluating materials of construction is operational. Fuel from a BWR (Big Rock Point) yielded more fine solid residue on dissolution than in previous tests with PWR fuel. Two additional parametric voloxidation tests with H.B. Robinson fuel compared air vs pure oxygen atmospheres at 550{sup 0}C; overall tritium release and subsequent fuel dissolution were equivalent. Thorium dissolution studies: the dissolution rate of thoria in fluoride-catalyzed 8 to 14 M HNO{sub 3} (100{sup 0}C) was max between 0.04 to 0.06 M HF; at higher fluoride concentrations, ThF{sub 4}.5H{sub 2}O precipitated. The rate of zircaloy dissolution continued to increase with increasing fluoride concentration. Stainless-steel-clad (Th,U)0{sub 2} fuel rods irradiated in the NRX reactor were sheared, voloxidized, and dissolved. {le}10% of the tritium was released during voloxidation in air at 600{sup 0}C. Carbon-14 removal from off-gas and fixation: carbon dioxide removal with Linde 13X molecular sieves to less than 100 ppB was experimentally verified using 300 ppM CO in air. Decontamination factors from 3000 to 7500 were obtained for CO{sub 2} removal in the gas-slurry stirred-tank reactor with CA(OH){sub 2}.or Ba(0H){sub 2}/sup .8H2O./. With Ba(OH){sub 2}.H{sub 2}0{sup 2} in a fixed-bed column, decontamination factors of about 30,000 were obtained.
Date: August 1, 1978
Creator: Vondra, B.L.
Partner: UNT Libraries Government Documents Department

Plutonium(IV) oxalate precipitation and calcination process for plutonium nitrate to oxide conversion

Description: The Plutonium(IV) Oxalate Precipitation and Calcination Process for converting plutonium nitrate to plutonium oxide is described for a 100-kg plutonium per day (Pu/day/ throughput facility. Block flow diagrams, equipment flowsheets, and stream material balances are included. Advantages and disadvantages of the process, additional research and development necessary, and history of the process are also discussed. This report is one of a series describing various processes for converting plutonium nitrate to oxide. This information in this report should be used when comparing the various processes, and as a starting point for development of a prototype or plant-scale facility.
Date: July 26, 1978
Creator: Greintz, R.M. & Neal, D.H.
Partner: UNT Libraries Government Documents Department

AFCT/TFCT/ISFS Program. Technical progress report for the period April 1, 1978--June 30, 1978

Description: This is the tenth in a series of quarterly progress reports on studies performed for the Alternate Fuel Cycle Technologies/Thorium Fuel Cycle Technologies/International Spent Fuel Receipt and Storage (AFCT/TFCT/ISFS) Program. This program provides information needed by industry to close the back end of the power reactor fuel cycle. During the past quarter, studies were conducted in the following tasks: thorium resource price analyses; spent fuel receipt and storage; investigation of air cleaning processes for removing TBP from off-gas streams; study of iodine chemistry in process solutions, high-level waste treatment; electropolishing to decontaminate metallic waste from alternate and thorium converter fuel cycles; U.S. scale transport, dispersion and removal model comparison; safety criticality experiments; and criticality research in support of thorium fuel cycle.
Date: August 1978
Creator: Hill, O. F.
Partner: UNT Libraries Government Documents Department

AFCT/TFCT/ISFS Program. Technical progress report for the period October 1, 1977--December 31, 1977

Description: This is the eighth in a series of quarterly progress reports on studies performed for the Alternate Fuel Cycle Technologies/Thorium Fuel Cycle Technologies/International Spent Fuel Receipt and Storage (AFCT/TFCT/ISFS) Program, formerly the LWR Fuel Recycle Program. This program is designed to provide information needed by industry to close the back end of the power reactor fuel cycle. During the past quarter, studies were conducted in the following tasks: Survey of Current Technology of Fuel Handling Techniques; Investigation of Air Cleaning Processes for Removing Tributyl Phosphate (TBP) from Off-Gas Streams; Study of Iodine Chemistry in Process Solutions; Electropolishing to Decontaminate Metallic Waste from Alternate and Thorium Converter Fuel Cycles; and U.S. Scale Transport, Dispersion and Removal Mode Comparison Safety Criticality Experiments. (11 figs., 7 tables)
Date: February 1978
Creator: Hill, O. F.
Partner: UNT Libraries Government Documents Department

Particle beam fusion research at Sandia National Laboratories

Description: Sandia`s Particle Beam Fusion Program is investigating several driver options, based on pulsed power technology, with the goal of demonstrating a practical ignitor for Inertial Confinement Fusion (ICF) Reactors. The interrelated aspects of power conditioning and compression, beam-target interaction, and target ignition are being studied. The issues of efficiency, reliability and multiple pulse capability are being integrated into the program to provide a viable approach to an experimental power reactor. On a shorter time scale the authors expect to derive important military-related benefits from attendant research and facility development. The two most important advantages of pulsed power driven fusion are the inherent low cost and high efficiency of high current particle accelerators. However, comparison of the relative merits of particle beams and focused laser beams must include many other factors such as beam transport, and target coupling, as well as target design and fabrication. These issues are being investigated to determine if the perceived practical benefits of particle beam fusion can indeed be realized. The practical considerations are exemplified in a comparison of the leading ICF drivers. The plan being followed by Sandia involves using the Electron Beam Fusion Accelerator (EBFA) to meet three objectives by 1985: significant burn using EBFA 1, net energy gain based on an upgrade of EBFA to the 2 megajoule (MJ) level (EBFA 2), and demonstration of a single module of EBFA 2 operated in the repetitive pulse mode. These goals are dependent, of course, on success in solving several key technical problems under investigation. If these technical problems can be solved, then practical applications to fusion power could be considered. The potential for these applications has been studied using economic models that allow one to derive the cost of power based on various assumptions.
Date: December 31, 1978
Partner: UNT Libraries Government Documents Department