Following the introduction this report contains the following two sections: (1) field work completed to date; and (2) results and conclusions to date. Field work covers: (1) review of past efforts; (2) well to well tracer testing: (3) injection program; (4) logging program; (5) pressure falloff testing; and (6) injectivity profiles. Results and conclusions cover: (1) injection pressure; (2) temperature at the producers; (3) injectivity profiles; (4) tracer studies; (5) carbon/oxygen logging; (6) well testing; and (7) production data. 12 references, 11 figures, 2 tables.

We present here computational results using second order Godunov methods for time-dependent Eulerian gas dynamics with a general (convex) equation of state. 5 refs., 5 figs.

Hitachi Ltd. of Japan, with the assistance of the Bechtel Group, Inc. and the General Electric Company of the US, initiated a conceptual design study of a compact tank-type LMFBR. The Bechtel work concentrated on layout of the nuclear island (NI), and its orientation with respect to the Control (CB) and Turbine (TGB) Buildings. This joint effort was carried out during 1982 and 1983 in four steps. Each step produced improvements in the design and reduced the plant size and cost. This paper described the design evolution and the final result with respect to Bechtel's development of the NI layout.

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "J, P. Trappers is built of thick, peeled logs from southeastern Oklahoma."

This report summarizes the survey work conducted by Argonne National Laboratory on the design and details of major penetrations in 22 nuclear power plants. The survey includes all containment types and materials in current use. It also includes details of all types of penetrations (except for electrical penetration assemblies and valves) and the seals and gaskets used in them. The report provides a test matrix for testing major penetrations and for testing seals and gaskets in order to evaluate their leakage potential under severe accident conditions.

Two tracer tests on doublet systems in a fractured geothermal system were carried out in Klamath Falls, Oregon. The purpose of the tests were to obtain data which would lead to information about the reservoir and to test the applicability of current tracer flow models. The results show rapid breakthrough times and indicate fracture flow with vigorous mixing of injector fluid before production of same. This leads to the idea that thermal breakthrough is not directly related to tracer breakthrough in the Klamath Union doublet system. There has been no long-term enthalpy loss from exploiting the resource for 40 years. In order to reduce the data, models were developed to analyze the results. Along with a porous media flow model two mathematical models developed to analyze fractured geothermal systems are used to help decipher the various tracer return curves. The flow of tracers in doublet systems was investigated. A mathematical description is used for tracer flow through fractures as a function of time and various nonlinear parameters which can be found using a curve fitting technique. This allows the reservoir to be qualitatively defined. These models fit the data well, but point to the fact that future improvement needs to …

A tank type plant has been designed that offers compactness, high reliability under seismic and thermal transients, and a safety design approach that provides a balance between public safety and plant availability. This report provides a description of the design philosophy and safety features of the reactor.

The applicability and accuracy of the approximation for Taylor Dispersion was experimentally determined for the diffusion of a chemical tracer in flow through a fracture. 12 refs., 16 figs., 10 tabs. (ACR)

Retention processes such as adsorption and diffusion into an immobile region can effect tracer movement through a fractured reservoir. This study has conducted experimental work and has developed a two-dimensional model to characterize retention processes. A method to directly determine some important flow parameters, such as the fracture aperture, from the analysis of tracer tests has been developed as a result of the new two-dimensional model. The experimental work consisted of batch experiments designed to both reproduce earlier work and to determine the magnitude of the retention effects. Negligible retention was observed from which it was concluded that the batch experiments were not sensitive enough and that more sensitive flowing tests were needed. A two-dimensional model that represents a fractured medium by a mobile region, in which convention, diffusion, and adsorption are allowed, and an immobile region in which only diffusion and adsorption are allowed has been developed. It was possible to demonstrate how each of the mass-transfer processes included in the model affect tracer return curves by producing return curves for any set of the defining variables. Field data from the New Zealand was numerically fit with the model. The optimum values of the parameters determined from curve fitting …

Depletion models for liquid-dominated geothermal reservoirs are derived and presented. The depletion models are divided into two categories: confined and unconfined. For both cases depletion models with no recharge (or influx), and depletion models including recharge, are used to match field data from the Svartsengi high temperature geothermal field in Iceland. The influx models included with the mass and energy balances are adopted from the petroleum engineering literature. The match to production data from Svartsengi is improved when influx was included. The Schilthuis steady-state influx gives a satisfactory match. The finite aquifer method of Fetkovitch, and the unsteady state method of Hurst gave reasonable answers, but not as good. The best match is obtained using Hurst simplified solution when lambda = 1.3 x 10{sup -4} m{sup -1}. From the match the cross-sectional area of the aquifer was calculated as 3.6 km{sup 2}. The drawdown was predicted using the Hurst simplified method, and compared with predicted drawdown from a boiling model and an empirical log-log model. A large difference between the models was obtained. The predicted drawdown using the Hurst simplified method falls between the other two. Injection has been considered by defining the net rate as being the production rate …

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "Azure Robinson, left, and Timmy Wheeler, right, of Oklahoma Children's Memorial Hospital Burn Center, look at a prairie dog held by Pandy Ammann."

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "Highway contractors are proceeding steadily with construction of Oklahoma City's West Bypass following an increase in gasoline taxes paid by Oklahoma motorists."

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "Carefully checking their bicycle gear are, from left, Melissa Osmond, Michelle Matthews and Leslie Osmond."

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "Cache, Okla. --Eagle Park."

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "Amber-Pocasset's Tracy Elliott outreaches Webbers Falls' Leanne Spears (53) of the East as the pair dive for a ball in Friday night's Small Schools All-Star Girls Basketball Game at Lawton."

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "Cyclists Kelly Barnes, left, Jenifer Cox and Margaret Holden review their itinerary."

Photograph used for a newspaper owned by the Oklahoma Publishing Company.

The environmental levels of radioactivity and other pollutants found in the vicinity of BNL during 1983 are summarized. 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; radioactivity of air particulates; tritium concentrations; the amounts and concentrations of radioactivity in and the water quality of the stream into which liquid effluents are released; the concentrations of radioactivity in biota from the stream; the concentrations of radioactivity in and the water quality of ground waters underlying the Laboratory; and concentrations of radioactivity in milk samples obtained in the vicinity of the Laboratory. The amounts of radioactivity released in airborne and liquid effluents from laboratory facilities to the environment were within allowable standards as stipulated in DOE Order 5480.1. Other pollutants, such as metals, organic compounds, etc., in the effluents released from the Laboratory were well below federal, state and local standards as applied to site specific conditions. 34 references, 9 figures, 17 tables.

In the 1983 Laser Program Annual Report we present the accomplishments and unclassified activities of the Laser Program at Lawrence Livermore National laboratory (LLNL) for the year 1983. It should be noted that the report, of necessity, is a summary, and more detailed expositions of the research can be found in the many publications and reports authored by staff members in the Laser Program. The purpose of this report is to present our work in a brief form, but with sufficient depth to provide an overview of the analytical and experimental aspects of the LLNL Inertial-Confinement Fusion (ICF) Program. The format of this report is basically the same as that of previous years. Section 1 is an overview and highlights the important accomplishments and directions of the Program. Sections 2 through 7 provide the detailed information on the various major parts of the Program: Laser Systems and Operations, Target Design, Target Fabrication, Fusion Experiments, Laser Research and Development, and Energy Applications.

We calculate analytically the expected tune shifts due to systematic sextupole and decapole errors in the SSC dipoles of reference design A at an energy of 20 TeV. The momentum-dependent tune shift due to sextupole error is d nu/sub x/ = -0.0557 for ..delta..p/p = +-2 x 10/sup -5/. The random sextupole component in the SSC dipoles ..delta..b/sub 2/ should be less than 5 x 10/sup -4/.

This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held October 17 through November 4, 1983, at Santa Fe and Los Alamos, New Mexico and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a State system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1983 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, the Battelle Pacific Northwest Laboratory, Westinghouse Fast Flux Test Facility Visitor Center, and Washington Public Power System nuclear reactor facilities in Richland, Washington. Individual presentations were indexed for inclusion in the Energy Data Base.

A review is given of E/sub T//sup 0/ and neutral pion spectra from various interactions. Inclusive single particle production at large transverse momentum from heavy nuclear targets at Fermilab and at ISR are briefly discussed, followed by some results of measurement of transverse energy emission in the central region of pA collisions. An experiment at ISR is described in which the total neutral energy emitted in the central region was measured using an electromagnetic shower counter which detected the photons from the decays of neutral pions and neutral etas. The apparatus is described and selection criteria are given. Resulting energy spectra are given. Multiplicity distributions were related using the Wounded Nucleon Model. (LEW)

Linear boundary detection has received considerable attention in the past. Although linear boundaries are frequently suspected and observed in well tests, conventional interpretation methods rely upon the development of two straight lines, which may not occur in practice. This report introduces two new semilog type curve matching methods for finding the distance to linear boundaries using buildup tests. Idealized curves are plotted from analytical solutions generated using the image well concept. These curves are then collapsed mathematically to a single type curve. By matching field data to the semilog type curve, the distance to a linear boundary may be estimated. The new methods have distinct advantages. The transition zone is the most important feature of the pressure response for type curve matching. Since development of the second straight line is not required, the range of interpretable tests is greatly extended. No estimates of reservoir characteristics are required to calculate the distance to the boundary because dimensionless parameters are used. 23 refs., 15 figs., 1 tab.

Progress in the following studies on radioactive waste management is reported: defense waste technology; Nuclear Waste Materials Characterization Center; waste isolation; and supporting studies. 58 figures, 22 tables.