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Orientation study of the Lake Sunapee area, New Hampshire. National Uranium Resource Evaluation Program
An orientation study was conducted in the area of Lake Sunapee, New Hampshire, in preparation for a hydrogeochemical and stream sediment reconnaissance in glacial terrain. The study was carried out by the Savannah River Laboratory as part of the National Uranium Resource Evaluation (NURE). Ground water, lake water, stream water, lake sediment, and stream sediment samples were collected at 188 sites. The concentrations of uranium and other elements were determined by neutron activation analysis. This report is issued in draft form, without detailed technical and copy editing. This was done to make the report available to the public before the end of the NURE program.
Date:
August 1, 1982
Creator:
Karfunkel, B. S. & Sargent, K. A.
System:
The UNT Digital Library
Analytical Chemistry Division. Annual progress report for period ending December 31, 1981
The functions of the Analytical Chemistry Division fall into three general categories: (1) analytical research, development, and implementation; (2) programmatic research, development and utilization; (3) technical support. The Division is organized into five major sections each of which may carry out any type of work falling into the thre categories mentioned above. Chapters 1 through 5 of this report highlight progress within the five sections which are: analytical methodology; mass and emission spectrometry; analytical technical support; bio/organic analysis section; and nuclear and radiochemical analysis. A short summary introduces each chapter to indicate work scope. Information about quality assurance and safety programs is presented in Chapter 6, along with a tabulation of analyses rendered. Chapter 7 covers supplementary activities. Chapter 8 is on presentation of research results (publications, articles reviewed or referred for periodicals). Approximately 56 articles, 31 proceedings publications and 33 reports have been published, and 119 oral presentations given during this reporting period.
Date:
April 1, 1982
Creator:
Lyon, W. S.
System:
The UNT Digital Library
Population dose commitments due to radioactive releases from nuclear-power-plant sites in 1978
Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1978. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each site. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each site is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitment from both liquid and airborne pathways ranged from a high of 200 person-rem to a low of 0.0004 person-rem with an arithmetic mean of 14 person-rem. The total population dose for allsites was estimated at 660 person-rem for the 93 million people considered at risk. The average individual dose commitment from all pathways on a site basis ranged from a low of 3 x 10/sup -6/ mrem to a high of 0.08 mrem. No attempt was made in this study to determine the maximum dose commitment received by any …
Date:
June 1, 1982
Creator:
Peloquin, R. A.; Schwab, J. D. & Baker, D. A.
System:
The UNT Digital Library
Electronics Engineering Department. Quarterly report No. 1, 1982
Six papers on the following subjects are included in this progress report: ultrasonic thermometry in oil shale retorts; an on-board recorder captures the performance of weapons designed for penetration of hard targets; pascal software structures achieve definite control of the 24 MFTF sustaining neutral-beam power supplies; a 7-MHz pulse height analyzer will analyze neutron spectra to measure plasma characteristics; a modified teletypewriter, controlled by a simple interface, converts messages to Braille; and the aluminum-air battery may be able to replace gasoline as a power source for automobiles. A separate abstract was prepared for each of the papers. (LCL)
Date:
April 1, 1982
Creator:
unknown
System:
The UNT Digital Library
Thermonuclear model for x-ray transients
The thermonuclear evolution of a 1.41 M sub solar neutron star accreting both solar and metal-deficient mixtures of hydrogen, helium, and heavy elements at rates ranging from about 10/sup -11/ to 10/sup -10/ M sub solar per year is examined using a one-dimensional numerical model. The metal deficient compositions may result either from placement of the neutron star in a binary system with a Population II red giant or from gravitational settling of heavy ions in the accreted material. For such accretion rates and metallicities, hydrogen burning, mediated by the ..beta..-limited CNO cycle, is stable and leads to the accumulation of a thick helium layer with mass 10/sup 23/ to 10/sup 25/ g and temperature 0.7 less than or equal to T/sub 8/ less than or equal to 1.2. Helium ignition occurs under extremely degenerate circumstances and is catastrophically violent. In the lower t helium shells this runaway is propagated as a convective deflagration, for the thicker layers a detonation front is set up which steepens into a strong relativistic shock wave in the neutron star envelope. In all models greatly super-Eddington luminosities in the outer layers of the neutron star lead to a sustained epoch of radiatively driven mass …
Date:
January 1, 1982
Creator:
Wallace, R. K.; Woosley, S. E. & Weaver, T. A.
System:
The UNT Digital Library
LAMPF II - also a hyperon factory
The possibility of generating large numbers of hyperons via an intense 4.5 GeV/c K/sup -/ beam at LAMPF II is explored. The advantage of using a K/sup -/ beam over that of using a ..pi.. beam is examined. Hyperon fluxes and backgrounds are estimated and compared with those available from existing hyperon beams. Production mechanisms are briefly discussed.
Date:
June 1, 1982
Creator:
Sanford, T.W.L.
System:
The UNT Digital Library
Thermochemical water-splitting cycle, bench-scale investigations, and process engineering. Final report, February 1977-December 31, 1981
The sulfur-iodine water-splitting cycle is characterized by the following three reactions: 2H/sub 2/O + SO/sub 2/ + I/sub 2/ ..-->.. H/sub 2/SO/sub 4/ + 2HI; H/sub 2/SO/sub 4/ ..-->.. H/sub 2/O + SO/sub 2/ + 1/2 O/sub 2/; and 2HI ..-->.. H/sub 2/ + I/sub 2/. This cycle was developed at General Atomic after several critical features in the above reactions were discovered. These involved phase separations, catalytic reactions, etc. Estimates of the energy efficiency of this economically reasonable advanced state-of-the-art processing unit produced sufficiently high values (to approx.47%) to warrant cycle development effort. The DOE contract was largely directed toward the engineering development of this cycle, including a small demonstration unit (CLCD), a bench-scale unit, engineering design, and costing. The work has resulted in a design that is projected to produce H/sub 2/ at prices not yet generally competitive with fossil-fuel-produced H/sub 2/ but are projected to be favorably competitive with respect to H/sub 2/ from fossil fuels in the future.
Date:
May 1, 1982
Creator:
Norman, J.H.; Besenbruch, G.E.; Brown, L.C.; O'Keefe, D.R. & Allen, C.L.
System:
The UNT Digital Library
Sediment and radionuclide transport in rivers. Phase 3. Field sampling program for Cattaraugus and Buttermilk Creeks, New York
A field sampling program was conducted on Cattaraugus and Buttermilk Creeks, New York during April 1979 to investigate the transport of radionuclides in surface waters as part of a continuing program to provide data for application and verification of Pacific Northwest Laboratory's (PNL) sediment and radionuclide transport model, SERATRA. Bed sediment, suspended sediment and water samples were collected during unsteady flow conditions over a 45 mile reach of stream channel. Radiological analysis of these samples included gamma ray spectrometry analysis, and radiochemical separation and analysis of Sr-90, Pu-238, Pu-239, 240, Am-241 and Cm-244. Tritium analysis was also performed on water samples. Based on the evaluation of radionuclide levels in Cattaraugus and Buttermilk Creeks, the Nuclear Fuel Services facility at West Valley, New York, may be the source of Cs-137, Sr-90, Cs-134, Co-60, Pu-238, Pu-239, 240, Am-241, Cm-244 and tritium found in the bed sediment, suspended sediment and water of Buttermilk and Cattaraugus Creeks. This field sampling effort was the last of a three phase program to collect hydrologic and radiologic data at different flow conditions.
Date:
August 1, 1982
Creator:
Ecker, R. M.; Walters, W. H. & Onishi, Y.
System:
The UNT Digital Library
LAMPF transition region
After describing the transition region between the LAMPF drift-tube linac and side-coupled linac, we discuss the function of the region, its present shortcomings, and the need for a redesign. Then we present the new design, its advantages, and its expected performance. Included are detailed results of beam-dynamics studies giving the ranges of input- and output-beam shapes that can be successfully matched in the new transition region. To improve the present operation of the two linacs, we suggest small changes that will allow us to easily match the beam between the two linacs. Finally we describe the methods used in our beam-dynamic studies so that effects of future improvements to the new design can be examined.
Date:
June 1, 1982
Creator:
Sander, O. R.
System:
The UNT Digital Library
D7H-test results
Data were reduced from the voltage-time relations stored in files D7H001 to D7H090 on HP1000. The I-B calibration curve is included. The data base is shown and can be used by the 9845B. The data include the quench location, Q/sub 2/ layer 1 top, Q/sub 3/ layer 1 bottom and the quench current and its normalized value with respect to short sample, I/sub c/ = 4920A at 4.4 K, I/sub c/ = 6710 A at 1.8 K. The resistance (..cap omega../cm) was calculated using the propagation time according to the voltage change across the measured sections. The conductor potential length are L/sub 5/ /sub 9/ = 48.6 cm, L/sub 6/ /sub 10/ = 17.9 cm, L/sub 7/ /sub 11/ = 40.6 cm. The turn to turn velocity V/sub t/ was calculated dividing the nominal turn to turn distance (58 mil) by the propagation time (Trans. Time). The quench time T/sub q/ was measured from the time the resistive rise starts until the energy extraction system fires.
Date:
July 30, 1982
Creator:
Caspi, S.
System:
The UNT Digital Library
/sup 238/Pu fuel-form processes. Quarterly report, October-December 1981
Progress in the Savannah River /sup 238/Pu Fuel Form Program is summarized. Work during this period concentrated on the extensive cracking of the /sup 238/PuO/sub 2/ fuel form prior to encapsulation in the iridium containment shell for heat sources. This cracking results in increased recycle cost and decreased production efficiency. To better understand this cracking, Savannah River Laboratory (SRL) has made an extensive review of the development of /sup 238/PuO/sub 2/ fuel forms from small-scale Multi-hundred Watt (MHW) pellets through the current GPHS full-scale pellet production. Historically, /sup 238/PuO/sub 2/ fuel has almost always been uncracked after hot pressing in a graphite die, but has emerged cracked and fragile from the final heat-treatment furnace. The cracking tendency depends on the microstructure of the fuel form and on the hot pressing conditions used to fabricate it. In general, a microstructure of large intershard porosity is more desirable because it allows internal gas to escape more readily and it can absorb more reoxidation strain. Studies of the GPHS microstructure showed that the internal structures of typical GPHS Pellets fabricated at LANL and in the PEF differed significantly. The LANL pellets had severe density gradients and were extensively cracked.
Date:
May 1, 1982
Creator:
unknown
System:
The UNT Digital Library
Geologic evolution of the Jemez Mountains and their potential for future volcanic activity
Geophysical and geochemical data and the geologic history of the Rio Grande rift and the vicinity of the Jemez Mountains are summarized to determine the probability of future volcanic activity in the Los Alamos, New Mexico area. The apparent cyclic nature of volcanism in the Jemez Mountains may be related to intermittent thermal inputs into the volcanic system beneath the region. The Jemez lineament, an alignment of late Cenozoic volcanic centers that crosses the rift near Los Alamos, has played an important role in the volcanic evolution of the Jemez Mountains. Geophysical data suggest that there is no active shallow magma body beneath the Valles caldera, though magma probably exists at about 15 km beneath this portion of the rift. The rate of volcanism in the Jemez Mountains during the last 10 million years has been 5 x 10/sup -9//km/sup 2//y. Lava or ash flows overriding Laboratory radioactive waste disposal sites would have little potential to release radionuclides to the environment. The probability of a new volcano intruding close enough to a radioactive waste disposal site to effect radionuclide release is 2 x 10/sup -7//y.
Date:
January 1, 1982
Creator:
Burton, B. W.
System:
The UNT Digital Library
Uranium hydrogeochemical and stream-sediment reconnaissance of the Bettles NTMS quadrangle, Alaska
This report presents results of a Hydrogeochemical and Stream Sediment Reconnaissance (HSSR) of the Bettles NTMS quadrangle, Alaska. In addition to this abbreviated data release, more complete data are available to the public in machine-readable form. These machine-readable data, as well as quarterly or semiannual program progress reports containing further information on the HSSR program in general, or on the Los Alamos National Laboratory (LANL) portion of the program in particular, are available from DOE's Technical Library at its Grand Junction Area Office. Presented in this data release are location data, field analyses, and laboratory analyses of several different sample media. For the sake of brevity, many field site observations have not been included in this volume; these data are, however, available on the magnetic tape. Appendices A and B describe the sample media and summarize the analytical results for each medium. The data have been subdivided by one of the Los Alamos National Laboratory sorting programs of Zinkl and others (1981a) into groups of stream-sediment and lake-sediment samples. For each group which contains a sufficient number of observations, statistical tables, tables of raw data, and 1:1,000,000 scale maps of pertinent elements have been included in this report. Also included …
Date:
February 1, 1982
Creator:
D'Andrea, R. F., Jr.; Zinkl, R. J.; Shettel, D. L., Jr.; Langfeldt, S. L. & Hardy, L. C.
System:
The UNT Digital Library
Low- to Moderate-Temperature Geothermal Resource Assessment for Nevada: Area Specific Studies, Pumpernickel Valley, Carlin and Moana. Final Report June 1, 1981-July 31, 1982
Geological, geophysical and geochemical surveys were used in conjunction with temperature gradient hole drilling to assess the geothermal resources in Pumpernickel Valley and Carlin, Nevada. This program is based on a statewide assessment of geothermal resources that was completed in 1979. The exploration techniques are based on previous federally-funded assessment programs that were completed in six other areas in Nevada and include: literature search and compilation of existing data, geologic reconnaissance, chemical sampling of thermal and non-thermal fluids, interpretation of satellite imagery, interpretation of low-sun angle aerial photographs, two-meter depth temperature probe survey, gravity survey, seismic survey, soil-mercury survey, and temperature gradient drilling.
Date:
January 1, 1982
Creator:
Trexler, D. T.; Flynn, T.; Koenig, B. A.; Bell, E. J. & Ghusn, G., (Jr.)
System:
The UNT Digital Library
Uranium hydrogeochemical and stream-sediment reconnaissance of the Juneau NTMS quadrangle, Alaska
This report presents results of a Hydrogeochemical and Stream Sediment Reconnaissance (HSSR) of the Juneau NTMS quadrangle, Alaska. In addition to this abbreviated data release, more complete data are available to the public in machine-readable form. These machine-readable data, as well as quarterly or semiannual program progress reports containing further information on the HSSR program in general, or on the Los Alamos National Laboratory (LANL) portion of the program in particular, are available from DOE's Technical Library at its Grand Junction Area Office. Presented in this data release are location data, field analyses, and laboratory analyses of several different sample media. For the sake of brevity, many field site observations have not been included in this volume; these data are, however, available on the magnetic tape. Appendices A and B describe the sample media and summarize the analytical results for each medium. The data have been subdivided by one of the Los Alamos National Laboratory sorting programs of Zinkl and others (1981a) into stream-sediment and lake-sediment samples. For each group which contains a sufficient number of observations, statistical tables, tables of raw data, and 1:1,000,000 scale maps of pertinent elements have been included in this report. Also included are maps …
Date:
April 1, 1982
Creator:
Zinkl, R. J.; Shettel, D. L., Jr.; Langfeldt, S. L.; Hardy, L. C. & D'Andrea, R. F., Jr.
System:
The UNT Digital Library
Gamma densitometer for measuring Pu density in fuel tubes
A fuel-gamma-densitometer (FGD) has been developed to examine nondestructively the uniformity of plutonium in aluminum-clad fuel tubes at the Savannah River Plant (SRP). The monitoring technique is ..gamma..-ray spectroscopy with a lead-collimated Ge(Li) detector. Plutonium density is correlated with the measured intensity of the 208 keV ..gamma..-ray from /sup 237/U (7d) of the /sup 241/Pu (15y) decay chain. The FGD measures the plutonium density within 0.125- or 0.25-inch-diameter areas of the 0.133- to 0.183-inch-thick tube walls. Each measurement yields a density ratio that relates the plutonium density of the measured area to the plutonium density in normal regions of the tube. The technique was used to appraise a series of fuel tubes to be irradated in an SRP reactor. High-density plutonium areas were initially identified by x-ray methods and then examined quantitatively with the FGD. The FGD reliably tested fuel tubes and yielded density ratios over a range of 0.0 to 2.5. FGD measurements examined (1) nonuniform plutonium densities or hot spots, (2) uniform high-density patches, and (3) plutonium density distribution in thin cladding regions. Measurements for tubes with known plutonium density agreed with predictions to within 2%. Attenuation measurements of the 208-keV ..gamma..-ray passage through the tube walls agreed …
Date:
January 1, 1982
Creator:
Winn, Willard G.
System:
The UNT Digital Library
Analysis of n+/sup 165/Ho and /sup 169/Tm reactions
Experimental data for neutron-induced reactions on /sup 165/Ho and /sup 169/Tm have been theoretically analyzed in preparation for calculations on the unstable isotopes of Tm. A set of deformed optical model parameters was determined from measurements of s- and p-wave neutron strength functions, total cross sections, elastic angular distributions, and 16-MeV proton scattering to the /sup 165/Ho ground and first excited states. The parameters for the /sup 165/Ho and /sup 169/Tm nuclei were linked by means of an isospin term in the real and imaginary well depths, together with adjustment of the ..beta../sub 2/ and ..beta../sub 4/ deformation parameters based on systematics in this mass region. Transmission coefficients from this analysis were used in Hauser-Feshbach statistical model calculations of the /sup 169/Tm(n,..gamma..) cross section as well as the /sup 169/Tm(n,2n) and (n,3n) cross sections to 23 MeV, after application of suitable preequilibrium corrections. The results of these calculations are in good agreement with most of the available experimental data on /sup 165/Ho and /sup 169/Tm.
Date:
January 1, 1982
Creator:
Young, P. G.; Arthur, E. D.; Philis, C.; Nagel, P. & Collin, M.
System:
The UNT Digital Library
Evaluation of uranium geochemical anomalies in the Greenville, SC, area, Greenville 1/sup 0/ x 2/sup 0/ Quadrangle (Greenville and Greer). National Uranium Resource Evaluation Program
The Savannah River Laboratory (SRL) was involved in the National Uranium Resource Evaluation (NURE) from 1974 through 1981. The SRL role was to design and conduct and report the data from a geochemical reconnaissance of almost half the continental United States. The purpose of the work was to provide a basis for evaluation of the uranium potential of areas and to identify areas meriting some conventional geologic followup. More than 275,000 samples of stream sediment, soil, vegetation, and ground or surface water were collected in the program. As part of the development program to support interpretation of the geochemical data, SRL conducted a series of field studies to verify anomalies identified in the reconnaissance data. Subcontractors were selected to conduct field scintillometer surveys, compile geologic maps, collect additional samples, or provide other services as needed for a given study. This report presents the results of a small study in the Greenville 1/sup 0/ x 2/sup 0/ quadrangle. The study was conducted for SRL by Kenneth A. Sargent. This study is one of a series designed to provide a basis for interpretation of SRL regional geochemical reconnaissance data. It contains the results of a four-channel gamma spectrometer survey of an area …
Date:
August 1, 1982
Creator:
Sargent, K. A.
System:
The UNT Digital Library
Dynamic performance of packed-bed dehumidifiers: experimental results from the SERI desiccant test loop
Discussed are the design and construction of a desiccant test loop and results of tests with a silica-gel-packed bed. The test loop consists of two centrifugal fans, two duct heaters, a steam humidifier, 24.4m (80 ft) of 30-cm (12-in.) circular duct, instrumentation, and a test section. The loop is capable of testing adsorption and desorption modes at flow rates up to 0.340 kg/s (600 scfm) and at regeneration temperatures up to 120/sup 0/C (248/sup 0/F). Tests of a 74-cm(29-in.)-diameter, 3.2-cm(1.25-in.)-thick silica gel bed indicated that mass transfer occurs more readily in the adsorption direction than in the desorption direction. Pressure drop data indicated that the resistance of each of the two screens that hold the silica gel in place was equivalent to 2.5-cm(1-in.) of silica gel due to plugging. Results of the tests were also used to validate a SERI desiccant computer model, DESSIM.
Date:
August 1, 1982
Creator:
Kutscher, C F & Barlow, R S
System:
The UNT Digital Library
Some calculator programs for particle physics. [LEGENDRE, ASSOCIATED LEGENDRE, CONFIDENCE, TWO BODY, ELLIPSE, DALITZ RECTANGULAR, and DALITZ TRIANGULAR codes]
Seven calculator programs that do simple chores that arise in elementary particle physics are given. LEGENDRE evaluates the Legendre polynomial series ..sigma..a/sub n/P/sub n/(x) at a series of values of x. ASSOCIATED LEGENDRE evaluates the first-associated Legendre polynomial series ..sigma..b/sub n/P/sub n//sup 1/(x) at a series of values of x. CONFIDENCE calculates confidence levels for chi/sup 2/, Gaussian, or Poisson probability distributions. TWO BODY calculates the c.m. energy, the initial- and final-state c.m. momenta, and the extreme values of t and u for a 2-body reaction. ELLIPSE calculates coordinates of points for drawing an ellipse plot showing the kinematics of a 2-body reaction or decay. DALITZ RECTANGULAR calculates coordinates of points on the boundary of a rectangular Dalitz plot. DALITZ TRIANGULAR calculates coordinates of points on the boundary of a triangular Dalitz plot. There are short versions of CONFIDENCE (EVEN N and POISSON) that calculate confidence levels for the even-degree-of-freedom-chi/sup 2/ and the Poisson cases, and there is a short version of TWO BODY (CM) that calculates just the c.m. energy and initial-state momentum. The programs are written for the HP-97 calculator. (WHK)
Date:
January 1, 1982
Creator:
Wohl, C.G.
System:
The UNT Digital Library
dc glow-discharge cleaning for accelerator
Average pressure of 1 x 10/sup -11/ torr and vacuum stability are necessary for the successful operation of the proton storage rings such as ISABELLE. Vacuum degassing at high temperature and in situ bake-out will reduce the thermoout-gassing rate of the beam tubes to approx. 10/sup -13/ Tl/cm/sup 2/ sec, therefore achieving the required static pressure. The vacuum instability caused by beam-induced ion desorption can be solved by dc glow discharge cleaning. With evidence from this study, the present understanding of glow discharge in a cylindrically symmetric geometry is reviewed. Argon and argon/oxygen mixture serve as plasmas in the glow. The role of oxygen in cleaning the beam tubes during the glow discharge is demonstrated experimentally. Glow discharge cleaning with and without bake-out is also studied.
Date:
January 1, 1982
Creator:
Chou, T. S. & Hseuh, H. C.
System:
The UNT Digital Library
Disruption model
Calculations of disruption time and energy dissipation have been obtained by simulating the plasma as an electrical conducting loop that varies in resistivity, current density, major radius. The calculations provide results which are in good agreement with experimental observations. It is believed that this approach allows engineering designs for disruptions to be completed in large tokamaks such as INTOR or FED.
Date:
July 1, 1982
Creator:
Murray, J. G. & Bronner, G.
System:
The UNT Digital Library
Community heat-pump system, Klamath County, Oregon
The possibility of heating 47 proposed homes on a new development site using ground water source heat pumps is discussed. The Shield Crest tract is located approximately five miles southeast of downtown Klamath Falls, Oregon. Two moderate capacity (greater than 450 gpm) warm water wells are located on the property. The pumping temperatures are 78/sup 0/F for No. 2 Well, neither temperature is hot enough for direct space heating. Temperature profiles of the wells indicate that a temperature hot enough for direct heating (about 110/sup 0/F or above) cannot be found at reasonable depth. Since direct geothermal heating is not a practical alternative, the tract will be all-electric since this is the only energy source in the area. This study addresses the economic feasibility of a community heat pump system that would reduce the amount of electrical energy required to service the homes.
Date:
March 1, 1982
Creator:
unknown
System:
The UNT Digital Library
Radon and aerosol release from open-pit uranium mining
The quantity of /sup 222/Rn (hereafter called radon) released per unit of uranium produced from open pit mining has been determined. A secondary objective was to determine the nature and quantity of airborne particles resulting from mine operations. To accomplish these objectives, a comprehensive study of the release rates of radon and aerosol material to the atmosphere was made over a one-year period from April 1979 to May 1980 at the Morton Ranch Mine which was operated by United Nuclear Corporation (UNC) in partnership with Tennessee Valley Authority (TVA). The mine is now operated for TVA by Silver King Mines. Morton Ranch Mine was one of five open pit uranium mines studied in central Wyoming. Corroborative measurements were made of radon flux and /sup 226/Ra (hereafter called radium) concentrations of various surfaces at three of the other mines in October 1980 and again at these three mines plus a fourth in April of 1981. Three of these mines are located in the Powder River Basin, about 80 kilometers east by northeast of Casper. One is located in the Shirley Basin, about 60 km south of Casper, and the remaining one is located in the Gas Hills, approximately 100 km west …
Date:
August 1, 1982
Creator:
Thomas, V.W.; Nielson, K.K. & Mauch, M.L.
System:
The UNT Digital Library