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0. 20-m (8-in.) Primary Burner Development Report

Description: High-Temperature Gas-Cooled Reactors (HTGRs) utilize graphite-base fuels. Fluidized-bed burners are being employed successfully in the experimental reprocessing of these fuels. The primary fluidized-bed burner is a unit operation in the reprocessing flowsheet in which the graphite moderator is removed. A detailed description of the development status of the 0.20-m (8-in.) diameter primary fluidized-bed burner as of July 1, 1977 is presented. Experimental work to date performed in 0.10; 0.20; and 0.40-m (4, 8, and 16 in.) diameter primary burners has demonstrated the feasibility of the primary burning process and, at the same time, has defined more clearly the areas in which additional experimental work is required. The design and recent operating history of the 0.20-m-diameter burner are discussed, with emphasis placed upon the evolution of the current design and operating philosophy.
Date: December 1977
Creator: Stula, R. T.; Young, D. T. & Rode, J. S.
Partner: UNT Libraries Government Documents Department
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2-mm microwave interferometer

Description: A 2-mm microwave interferometer has been developed, and phase shift measurements have been made on the Baseball II experiment. The interferometer system employs a 140-GHz receiver for double down conversion of the plasma signal to a 60-MHz, IF frequency. The 140-GHz references signal is also down-converted and compared with the plasma signal to provide the desired phase change of the signal passing through the plasma. A feedback voltage from a 60-MHz discriminator to a voltage-controlled oscillator in the receiver provides frequency stability of the 60-MHz IF signals.
Date: March 1, 1977
Creator: Futch, A. H. & Mortensen, W. K.
Partner: UNT Libraries Government Documents Department
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2-MW plasmajet facility thermal tests of concrete. [PWR and BWR]

Description: A test was made in the 2-Megawatt Plasmajet Facility to obtain experimental data relative to the thermal response of concrete to incident heat flux. 14.6 cm diameter by 8.0 cm long concrete cylinders were positioned in a supersonic flow of heated nitrogen from an arc heater. The end of the concrete cylinders impacted by the flow were subjected to heat fluxes in the range of 0.13 to 0.35 kW/cm/sup 2/. Measurements included cold wall surface heat flux and pressure distributions, surface and indepth temperatures, ablation rates, and surface emission spectrographs. The test was part of the Sandia light water reactor safety research program and complements similar tests made in the Radiant Heat Facility at heat fluxes from 0.03 to 0.12 kW/cm/sup 2/. A description of the tests and a tabulation of test data are included.
Date: July 1, 1977
Creator: Goin, Kenneth L.
Partner: UNT Libraries Government Documents Department
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3-D nonlinear evolution of MHD instabilities

Description: The nonlinear evolution of ideal MHD internal instabilities is investigated in straight cylindrical geometry by means of a 3-D initial-value computer code. These instabilities are characterized by pairs of velocity vortex cells rolling off each other and helically twisted down the plasma column. The cells persist until the poloidal velocity saturates at a few tenths of the Alfven velocity. The nonlinear phase is characterized by convection around these essentially fixed vortex cells. For example, the initially centrally peaked temperature profile is convected out and around to form an annulus of high temperature surrounding a small region of lower temperature. Weak, centrally localized instabilities do not alter the edge of the plasma. Strong, large-scale instabilities, resulting from a stronger longitudinal equilibrium current, drive the plasma against the wall. After three examples of instability are analyzed in detail, the numerical methods and their verification are discussed.
Date: March 1, 1977
Creator: Bateman, G.; Hicks, H. R. & Wooten, J. W.
Partner: UNT Libraries Government Documents Department
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10-75-kWe-reactor-powered organic Rankine-cycle electric power systems (ORCEPS) study. Final technical report

Description: This 10-75 kW(e) Reactor-ORCEPS study was concerned with the evaluation of several organic Rankine cycle energy conversion systems which utilized a /sup 235/U-ZrH reactor as a heat source. A liquid metal (NaK) loop employing a thermoelectric converter-powered EM pump was used to transfer the reactor energy to the organic working fluid. At moderate peak cycle temperatures (750/sup 0/F), power conversion unit cycle efficiencies of up to 25% and overall efficiencies of 20% can be obtained. The required operating life of seven years should be readily achievable. The CP-25 (toluene) working fluid cycle was found to provide the highest performance levels at the lowest system weights. Specific weights varies from 100 to 50 lb/kW(e) over the power level range 10 to 75 kW(e). (DLC)
Date: March 30, 1977
Partner: UNT Libraries Government Documents Department
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40 kW of solar cell modules for the Large Scale Production Task, a Low Cost Silicon Solar Array Project. Final technical report

Description: Forty kilowatts of solar cell modules was produced in this program. This is equivalent to 4123 modules. The average power output per module was 9.7 watts at 16.5 volts, 60/sup 0/C and 100 mW/cm/sup 2/. The peak production rate was 200 modules per week which is equal to 1.9 kW per week. This rate was sustained for over four and one-half months and is equivalent to 100 kW per year. The solar cell module design, electrical and power performance, module preproduction environmental test results, production and shipping schedule, program summary, and delivery are described. A cost analysis section is written. Particular emphasis on the percentage of labor and material utilized in constructing a solar cell module is presented. Also included are cost reduction recommendations. It was concluded from this program that volume production on the order of hundreds of kilowatts per year per company as a minimum is required to significantly reduce the price per watt for solar cell modules. Sensor Technology more than doubled its solar cell module manufacturing facilities since the completion of the JPL Block II procurement. Plans are being made for large scale expansion of our facilities to meet growing JPL/DOE procurements.
Date: December 1, 1977
Creator: Jones, G.T.
Partner: UNT Libraries Government Documents Department
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150 kWe solar-powered deep-well irrigation facility. Phase I. Preliminary design study. Final report

Description: Results of a preliminary design study for a solar-powered irrigation facility to be located on a farm between Phoenix and Tucson, Arizona, are presented. The ERDA-specified generic design criteria are detailed. A detailed systems analysis is presented, and preliminary designs of the thermal storage system, organic Rankine cycle power system, cooling water system, power distribution system, and collector foundation are given. Site layout and improvements are described, and a cost analysis of prototype and production units is included. Engineering drawings are included. (WHK)
Date: August 8, 1977
Partner: UNT Libraries Government Documents Department
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150-m measurement of 0. 880- to 100. 0-keV neutron transmissions through four samples of /sup 238/U

Description: In order to study the /sup 238/U + n total cross section, neutron transmissions through 0.076-, 0.254-, 1.080-, and 3.620-cm-thick samples of isotopically enriched /sup 238/U have been measured from 0.880 to 100.0 keV using a time-of-flight technique over a path length of 150 meters with the ORELA pulsed source and a 13-mm-thick Li-glass detector. The measurement is described in detail and both a listing and figures of the resulting transmissions are given. An absolute energy scale accurate to 2 parts in 10,000 was established.
Date: October 1, 1977
Creator: Olsen, D. K.; de Saussure, G.; Perez, R. B.; Difilippo, F. C.; Ingle, R. W. & Weaver, H.
Partner: UNT Libraries Government Documents Department
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236-Z canyon utilization study

Description: The 236-Z canyon contains equipment for repurification of plutonium and recovery of plutonium from scrap material. To meet production requirements of Fast Flux Test Facility/Clinch River Breeder Reactor oxide with the existing plant, several new pieces of equipment will be needed in the future. More storage space and a better accountability system are needed to support this increased production. The available canyon space needs to be utilized to its fullest in order to accommodate the new equipment. The purpose of this document is to identify the new pieces of equipment, show how they fit into the flowsheet, and locate them in the canyon.
Date: March 8, 1977
Creator: Dixon, D.R
Partner: UNT Libraries Government Documents Department
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250 keV resonance in the total neutron cross section of /sup 6/Li

Description: The energy of the observed maximum of the 250 keV resonance in the total neutron cross section of /sup 6/Li is measured to be 244.5 +- 1 keV relative to the velocity of light. The observed peak magnitude is 11.20 +- 0.20 b.
Date: June 1, 1977
Creator: Smith, A. B.; Guenther, P.; Havel, D. & Whalen, J. F.
Partner: UNT Libraries Government Documents Department
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324 building safety analysis report supplement

Description: Process engineering designs, major equipment and plant facilities to be utilized in commercial nuclear waste preparation and vitrification in the 324 Radiochemical Engineering Building are reviewed with regard to accident potential and consequences. This Safety Analysis Report Supplement compares calculated environmental doses anticipated from the Commercial Nuclear Waste Vitrification Project (CNWVP) routine operations with the average doses from past waste management operations conducted at the Hanford Project and finds them to be significantly less. The calculated CNWVP environmental doses are found to be far below presently applicable ERDA standards and standards proposed by the EPA for nuclear power operations. (DLC)
Date: June 24, 1977
Creator: Dodd, A. O. & Wittenbrock, N. G.
Partner: UNT Libraries Government Documents Department
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450/sup 0/F step transient thermal analysis of the LOFT pressurizer surge and spray line piping

Description: The LOFT pressurizer spray and surge line piping was analyzed for a 450/sup 0/F step change in fluid temperature. This transient was chosen to conservatively represent several pressurizer operating transients that had not previously been analyzed. These include temperature transients resulting from a 300/sup 0/F ..delta..T between pressurizer temperature and cold leg temperature, injection of a cooled (70/sup 0/F) slug of stagnant fluid into the hot (540/sup 0/F) spray line piping, and inflow of 100/sup 0/F primary coolant system water into the hot (480/sup 0/F) surge line piping.
Date: July 7, 1977
Creator: Tolan, B.J.
Partner: UNT Libraries Government Documents Department
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880 nanosecond particle in cell mover for the CDC 7600

Description: A very fast computational method of moving particles for one dimensional electrostatic plasma simulations using integer arithmetic is described. The cloud in cell method forms the basis of this technique. This paper is in the form of a compass compilable subroutine with comments and examples describing methods of using an entirely integer representation to gain up to an order of magnitude increase in speed over equivalent floating point Fortran coding. Integer arithmetic has several advantages over floating point arithmetic for one dimensional particle movers. The adds are much faster, and the binary numerical description allows the implementation of very simple boundary conditions if the simulation region extends from zero to a power of two. Furthermore, integer arithmetic makes very efficient use of each memory bit since there is no floating point exponent. Consequently, it becomes feasible and fast in long word length machines to pack the velocity and position of a particular particle into the same word, thus saving a factor of two in computer storage and/or 10. These advantages are combined with the fact that integer adds and logicals complete in only two computer cycles allowing nearly complete optimization of register and instruction interleaving. The measured timings on a CDC 7600 are 880 nanoseconds and 935 nanoseconds per particle for the periodic and general boundary condition sections respectively. Methods for adapting the technique to other computers are discussed.
Date: October 4, 1977
Creator: Estabrook, K. & Tull, J. E.
Partner: UNT Libraries Government Documents Department
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12G: code for conversion of isotope-ordered cross-section libraries into group-ordered cross-section libraries

Description: Many current reactor physics codes accept cross-section libraries in an isotope-ordered form, convert them with internal preprocessing routines to a group-ordered form, and then perform calculations using these group-ordered data. Occasionally, because of storage and time limitations, the preprocessing routines in these codes cannot convert very large multigroup isotope-ordered libraries. For this reason, the I2G code, i.e., ISOTXS to GRUPXS, was written to convert externally isotope-ordered cross section libraries in the standard file format called ISOTXS to group-ordered libraries in the standard format called GRUPXS. This code uses standardized multilevel data management routines which establish a strategy for the efficient conversion of large libraries. The I2G code is exportable contingent on access to, and an intimate familiarization with, the multilevel routines. These routines are machine dependent, and therefore must be provided by the importing facility. 6 figures, 3 tables.
Date: September 1, 1977
Creator: Resnik, W. M. II & Bosler, G. E.
Partner: UNT Libraries Government Documents Department
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1972 preliminary safety analysis report based on a conceptual design of a proposed repository in Kansas

Description: This preliminary safety analysis report is based on a proposed Federal Repository at Lyons, Kansas, for receiving, handling, and depositing radioactive solid wastes in bedded salt during the remainder of this century. The safety analysis applies to a hypothetical site in central Kansas identical to the Lyons site, except that it is free of nearby salt solution-mining operations and bore holes that cannot be plugged to Repository specifications. This PSAR contains much information that also appears in the conceptual design report. Much of the geological-hydrological information was gathered in the Lyons area. This report is organized in 16 sections: considerations leading to the proposed Repository, design requirements and criteria, a description of the Lyons site and its environs, land improvements, support facilities, utilities, different impacts of Repository operations, safety analysis, design confirmation program, operational management, requirements for eventually decommissioning the facility, design criteria for protection from severe natural events, and the proposed program of experimental investigations. (DLC)
Date: August 1, 1977
Creator: Blomeke, J. O.
Partner: UNT Libraries Government Documents Department
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1974 conceptual design description of a bedded salt pilot plant in southeast New Mexico

Description: The policy of the United States Atomic Energy Commission is to take custody of all commercial high-level radioactive wastes and maintain control of them in perpetuity. This policy (Title 10, Code of Federal Regulations, Part 50, Appendix F) requires that the high-level wastes from nuclear fuels reprocessing plants be solidified within five years after reprocessing and then shipped to a federal repository within ten years after reprocessing. Ultimate disposal sites and/or methods have not yet been selected and are not expected to be ready when waste deliveries begin about 1983. Therefore, the AEC plans to build an interim storage facility, called Retrievable Surface Storage Facility (RSSF), to store and isolate the waste from man and his environment until the suitability of the permanent repository is demonstrated and public acceptance has been established. Meantime, the AEC is proceeding with the study and development of an ultimate disposal method. Bedded salt is being considered for ultimate waste disposal, and work is in progress to develop a Bedded Salt Pilot Plant to demonstrate its acceptability. The pilot plant will permit in situ verification of laboratory work on the interaction of heat and radioactivity of the waste with the salt and surroundings. One concept of such a pilot facility is described.
Date: June 1, 1977
Partner: UNT Libraries Government Documents Department
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1976 Energy Resource Alternatives II Competition. Final report

Description: Descriptions of all the entries in the competition are presented. Competition rules and judging procedures are described. Entries consisted of team efforts from colleges and universities. The competition called for the student teams to develop means for producing electrical power sufficient to meet the needs of a single family home, using an energy source other than oil or natural gas. The electric power produced had to be economically realistic when compared to present energy sources.
Date: October 1, 1977
Creator: McGill, R.A.; Iannucilli, M.; Marshal, J.; Sununu, J.H.; Eschbach, J.E.; Anson, J. et al.
Partner: UNT Libraries Government Documents Department
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1976 environmental monitoring report

Description: The environmental levels of radioactivity and other environmental pollutants found in the vicinity of Brookhaven National Laboratory during 1976 are summarized. As an aid in the interpretation of the data, the amounts of radioactivity and other pollutants released in airborne and liquid effluents from Laboratory facilities to the environment are also indicated. The environmental data includes external radiation levels; radioactive air particulates; tritium and iodine concentrations; the amounts and concentrations of radioactivity in precipitation; the amounts and concentrations of radioactivity in and the quality of the stream into which liquid effluents are released; the concentrations of radioactivity in sediments and biota from the stream; the concentrations of radioactivity in and the quality of ground waters underlying the Laboratory; and concentrations of radioactivity in milk, grass, and soil samples obtained in the vicinity of the Laboratory. The external radiation level for 1976 at the north boundary of the Laboratory attributable to an ecology forest irradiation source was 74.4 mrem, or 14 percent of the applicable Radiation Protection Standard.
Date: April 1, 1977
Creator: Naidu, J. R.
Partner: UNT Libraries Government Documents Department
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1977 breeding bird censuses and vegetation surveys in two successional stages of oak--pine forest

Description: As part of a program to characterize the plant and animal life of the Laboratory site and surrounding areas, two breeding bird census plots were established in 1977 to document the occurrence and abundance of breeding species in two extreme successional stages of Long Island oak-pine forest. A 9.3-hectare plot located near the northeastern corner of the Laboratory site is composed of second growth oak-pine forest in a late successional stage. The second plot measures 9.7 hectares and is located in the scrub oak-pitch pine barrens at Westhampton. Each plot was surveyed with a transit and steel tape and marked with wooden stakes at 100-foot intervals. Quantitative vegetational surveys were made in each plot and all plant species identified. Tree composition was measured as a function of species and size. Shrub density, percent of ground cover and percent of canopy were also measured. The Laboratory plot contained 2100 trees of five species per hectare, 72% ground cover and 84% canopy coverage. The Westhampton plot contained only one tree species, Pitch Pine, at 366 trees per hectare, 92% ground cover and no canopy. Twelve census trips, mostly of two to three hour duration, were made in each plot. Each bird observed was located on a scale map of the plot. At the end of the season, the number of territories was determined from the distribution of sightings. Eighteen territorial bird species were found in the Laboratory plot with between 479 and 629 territorial males per km/sup 2/. In Westhampton, only five breeding species were present. Density was between 312 and 374 males per km/sup 2/. The Rufous-sided Towhee was the most common species in both plots. Future studies will document changes in both bird and plant species composition and abundance.
Date: December 1, 1977
Creator: Raynor, G. S.; Ruscica, J. J.; Clinton, J. H. & Larsen, D. L.
Partner: UNT Libraries Government Documents Department
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Ab initio effective core potentials including relativistic effects and their application to the electronic structure calculations of heavy atoms and molecules

Description: The effects of the 4f shell of electrons and the relativity of valence electrons are compared. The effect of 4f shell (lanthanide contraction) is estimated from the numerical Hartree-Fock (HF) calculations of pseudo-atoms corresponding to Hf, Re, Au, Hg, Tl, Pb and Bi without 4f electrons and with atomic numbers reduced by 14. The relativistic effect estimated from the numerical Dirac-Hartree-Fock (DHF) calculations of those atoms is comparable in the magnitude with that of the 4f shell of electrons. Both are larger for 6s than for 5d or 6p electrons. The various relativistic effects on valence electrons are discussed in detail to determine the proper level of the approximation for the valence electron calculations of systems with heavy elements. An effective core potential system has been developed for heavy atoms in which relativistic effects are included in the effective potentials.
Date: November 1, 1977
Creator: Lee, Y. S.
Partner: UNT Libraries Government Documents Department
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AC Transmission Line Field Measurements

Description: The concern in recent years over the environmental effects of electric and magnetic fields from high voltage transmission lines has also focused attention on the accuracy of measurements of these fields. Electric field meters are discussed in terms of theory of operation, parameters affecting performance, meter performance under field and laboratory conditions, and calibration procedures. The performance and calibration of magnetic field meters is described. (LCL)
Date: November 1, 1977
Creator: Kotter, F. R. & Misakian, M.
Partner: UNT Libraries Government Documents Department
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Accelerator Division Annual Report, Jan-Dec. 1975

Description: The Bevatron/Bevalac is operated, maintained, and continually improved as a national research facility for studies in nuclear science and in biology and medicine. Recent modifications have brought the 21-year-old synchrotron to the threshold of tremendously exciting new studies as the world's most powerful heavy-ion accelerator. In its Bevalac configuration, the machine capitalizes on the coupling of the SuperHILAC to the Bevatron via a 175-meter beam line. The SuperHILAC acts as an injector to provide the Bevatron with high-intensity beams of ions as heavy as argon. At the same time, the SuperHILAC is capable of delivering heavy-ion beams to its own group of experimenters through a computer-linked, time-share system of operation. Research efforts using the Bevalac have included a broad spectrum of nuclear science and cosmic-ray-simulation experiments, as well as intensive studies in biology and medicine aimed principally at diagnostic techniques and preclinical therapy studies for some forms of cancer.
Date: January 27, 1977
Creator: Lofgren, E. J.
Partner: UNT Libraries Government Documents Department
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Accelerator Division annual report, January 1976--September 1977

Description: Accelerator operations of the Bevatron/Bevalac, the SuperHILAC, and the 184-Inch Synchrocyclotron are described. The PEP storage ring is described. The superconducting accelerator (ESCAR) construction is reported, and experiments in heavy ion fusion are described. (GHT)
Date: January 1, 1977
Partner: UNT Libraries Government Documents Department
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Acceptable TRU packaging for interim storage and/or terminal isolation

Description: The major objective of ERDA Manual Chapter 0511 is responsible technical management of its radioactive wastes. To ensure long term technical management, this DOE responsibility initially begins with the generation of radioactive wastes in all DOE operations and includes all other attributes and parameters (waste processing, packaging, shipping and storage) over the lifetime of the radionuclides. Close examination of the entire waste management cycle clearly indicates that one of the most important constituents which minimizes the risk to man and his environment is an effective and totally acceptable waste package containment system. The retrievable storage site for defense transuranic waste at the Idaho National Engineering Laboratory has been accepting waste since November, 1970. Current DWPR planning calls for continuing use of the retrievable storage pad through FY-1987 with the WIPP facility attaining full operational status in FY-1988. In the FY-1976, 76A period over 107,000 ft of transuranic wastes were stored retrievably at INEL. This volume represents approximately 4000 drums of the 7.3 ft{sup 3} (55 gal.) size and 700 4 x 4 x 8` FRP coated plywood boxes on an annualized basis. At this waste generation rate, a rate which is probably conservative based upon known decontamination and decommissioning projects at Mound, Rocky Flats, LASL, Atomics International, LBL, and ORNL which will substantially increase TRU volumes before the WIPP becomes operational a total of approximately 32,000 drums and 5600 boxes will be added to storage at INEL. Based upon the difficult decisions presently being faced with respect to the acceptability to WIPP of the waste already in storage at INEL, it is imperative not to increase this scope of the problem by continuing to use waste containers which may well not be acceptable to the terminal isolation facility.
Date: October 31, 1977
Creator: Kokenge, B.R.
Partner: UNT Libraries Government Documents Department
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