This documentation describes the PIES Integrating Model as it existed on January 1, 1978. This volume contains two chapters. In Chapter I, Overview, the following subjects are briefly described: supply data, EIA projection series and scenarios, demand data and assumptions, and supply assumptions - oil and gas availabilities. Chapter II contains supply and demand data tables and sources used by the PIES Integrating Model for the mid-range scenario target years 1985 and 1990. Tabulated information is presented for demand, price, and elasticity data; coal data; imports data; oil and gas data; refineries data; synthetics, shale, and solar/geothermal data; transportation data; and utilities data.

This documentation describes the PIES Integrating Model as it existed on January 1, 1978. This Volume VI of six volumes is data documentation, containing the standard table data used for the Administrator's Report at the beginning of 1978, along with the primary data sources and the office responsible. It also contains a copy of a PIES Integrating Model Report with a description of its content. Following an overview chapter, Chapter II, Supply and Demand Data Tables and Sources for the Mid-range Scenario for Target Years 1985 and 1990, data on demand, price, and elasticity; coal; imports; oil and gas; refineries; synthetics, shale, and solar/geothermal; transportation; and utilities are presented. The following data on alternate scenarios are discussed: low and high demand; low and high oil and gas supply; refinery and oil and gas data assuming a 5% annual increase in real world oil prices. Chapter IV describes the solution output obtained from an execution of PIES.

Neutron detectors for flight test applications use either a photomultiplier tube (PMT) or a silicon photodiode as a light detector to monitor the light output of scintillation materials. Silicon diodes lack sensitivity, so PMT's are used in most low flux neutron applications. The SA 1690 is presently the only Sandia qualified PMT. It has a complex temperature response requiring the selection of a temperature compensation circuit during assembly to meet accuracy requirements. Results are presented of a study which was performed to evaluate the temperature stability of two other light detectors and to compare the results with the performance of the SA 1690.

A computer model was developed which predicts the axial temperature profile and heat flux at the outer surface of the test section of the Sodium Boiling Test Facility constructed by the Engineering Technology Division at ORNL. The model was in agreement with observed temperature profiles at furnace power levels representative of single phase, dual phase, and dry-out operations. A parametric study demonstrated the effect of sodium flow rate and surface emissivities on the predicted temperature profile. It was concluded that axial conduction in the Hastelloy tube and sodium must be incorporated into the model to improve accuracy.

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The test fire and data analysis of one technique to be utilized in lot characterization of PBX 9502 are described. The corner turning distance is expected to vary +- 2.1 mm on lot-to-lot variation, primarily due to density variations in the PBX 9502. The uncertainty of these measurements is estimated to be +- 0.2 mm as determined from errors of the systems and techniques employed in the tests.

This paper reports a first effort to examine the surface of the UCLA tokamaks, Microtor and Macrotor, by analyzing samples that have been exposed to plasma discharge and cleaning for long periods. The samples were sent to the Surface Science Section at the Pacific Northwest Laboratory (PNL). There, Auger electron spectrometry and sputter profile techniques were used to examine the samples, which had been handled in atmospheric conditions after being removed from the tokamak.

The report is in four sections, corresponding to the program elements: technology impacts, environmental control engineering, operational and environmental compliance and human health studies. Each section was abstracted and indexed separately. (JGB)

This handbook reviews the basic requirements of the use of liquid metals with emphasis on sodium which has the greatest current usage. It delineates the concepts necessary to design facilities both radioactive and nonradioactive for use with liquid metals. It further reviews the state-of-the-art in fire extinguishers and leak detection equipment and comments on their application and sensitivity. It also provides details on some engineering features of value to the designer of liquid metal facilities.

The results of work of Bendix Kansas City Division are made available in the form of technical reports that are processed through the DOE Technical Information Center in Oak Ridge. The present report lists the documents released by the Division, along with author and subject indexes. Drawing sets released are also listed. Locations of report collections in the U.S., other countries, and international agencies are provided. (RWR)

Most of the electricity generated in the U.S. and the heat used by industry, buildings, and homes are produced independently from the combustion of separate fuels. Cogeneration, the combined production of electricity and useful heat, could reduce significantly the total amount of fuel required. This report discusses areas of application and alternative technologies for cogeneration. Projections by various investigators indicate potential U.S. energy savings from 1 to 2% up to almost 10%. Several of the published estimates of potential energy conservation benefits from cogeneration are analyzed and reduced to common bases for comparison. Significant differences in the various projections arise from differences in estimating the size of the industrial steam demand and from divergent assumptions concerning the tractability of various implementation problems. 16 references.

ASBLT is a computer program consisting of DATATRAN MODULES which was used during the manufacturing phase of LWBR to collect and evaluate as-built data. The program was part of the LWBR fuel rod inspection process and produced sections of module assembly certification reports. ASBLT used fuel pellet, fuel rod and module assembly data to compute core inventories and to supply input to nuclear design programs for as-built core calculations.

The three areas of study emphasis to date are: (1) Physics implications for controls, (2) Computer simulation, and (3) Shutdown/aborts. This document reports on the FY 78 efforts (the first year of these studies) to address these problems. Transient scenario options for the startup of a tokamak are developed, and the implications for the control system are discussed. This document also presents a hybrid computer simulation (analog and digital) of the Impurity Study Experiment (ISX-B) which is now being used for corroborative controls investigations. The simulation will be expanded to represent a TNS/ETF machine.

The conceptual design and material study, Task 1 of this project is nearing completion. The primary objective of problem definition, in the form of a preliminary design specification, is complete. Several innovative concepts are being explored and compared. By the end of Task 1, the many alternative concepts will be narrowed considerably so that model studies of the most promising candidates may commence.

A selected annotated bibliography of 521 references was prepared as a part of a feasibility study of the extraction of uranium from seawater. For the most part, these references are related to the chemical processes whereby the uranium is removed from the seawater. A companion docment contains a similar bibliography of 471 references related to oceanographic and uranium extraction plant siting considerations, although some of the references are in common. The bibliography was prepared by computer retrieval from Chemical Abstracts, Nuclear Science Abstracts, Energy Data Base, NTIS, and Oceanic Abstracts. References are listed by author, country of author, and selected keywords.

Refinements of the design of the 50 MT/year Experimental Process System Development Unit (EPSDU) have been made and competitive bids have been received from mechanical, electrical, and structural contractors. Emergency procedures have been defined to counter a variety of contingencies disclosed in operations and safety reviews. Work continues with the fluidized-bed model to define conditions under which useful segregation of large particles can be obtained. Experimental work with an electrolytic cell for zinc chloride disclosed no significant increase in power efficiency by steps taken to increase electrolyte circulation. On the basis of materials compatibility and permeability tests, 310 stainless steel was chosen for the shell of the fluidized-bed reactor and SiC-coated graphite for the liner. Experiments on the volatility of lead, iron, and cadmium at the ppM level in zinc at its boiling point are being continued with provisions being made to withdraw molten samples so as to avoid segregation on freezing, believed to be the cause of earlier discrepancies.

Hastelloy alloy X has been a successful high-temperature structural material for more than two decades. Recently, Hastelloy alloy X sheet has been selected as a prime structural material for the proposed Brayton Isotope Power System (BIPS). The material also sees extensive application in the High-Temperature Gas-Cooled Reactor (HTGR). Design of these systems requires a detailed consideration of the high-temperature creep properties of this material. Therefore, available creep, creep-rupture, and relaxation data for Hastelloy alloy X were collected and analyzed to yield mathematical representations of the behavior for design use.

The Solar-Climatic Statistical Study was performed to provide statistical information on the expected future availability of solar and wind power at various nationwide sites. Historic data (SOLMET), at 26 National Weather Service stations reporting hourly solar insolation and collateral meteorological information, were interrogated to provide an estimate of future trends. Solar data are global radiation incident on a horizontal surface, and wind data represent wind power normal to the air flow. Selected insolation and wind power conditions were investigated for their occurrence and persistence, for defined periods of time, on a monthly basis. Information of this nature are intended as an aid to preliminary planning activities for the design and operation of solar and wind energy utilization and conversion systems. Presented in this volume are probability estimates of solar insolation and wind power, alone and in combination, occurring and persisting at or above specified thresholds, for up to one week, for each of the 26 SOLMET stations. Diurnal variations of wind power were also considered. Selected probability data for each station are presented graphically, and comprehensive plots for all stations are provided on a set of microfiche included in a folder in the back of this volume.

Residual stress measurements were made on a welded HP-9-4-20 steel test coupon to determine the potential of residual stress for producing stress corrosion cracking. X-ray diffraction and strain gauge rosettes were used to make the measurements. The results indicated that, under the conditions specified, the stress intensity produced by residual stress was one-fourth that required to produce stress corrosion cracking.

The power supply requirements for a 7-M major radius commercial tokamak reactor have been examined, using a system approach combining models of the reactor and poloidal coil set, plasma burn cycle and MHD calculations, and power supply characteristics and cost data. A conventional system using an MGF set and solid-state rectifier/inverter power supplies was studied in addition to systems using a homopolar generator, superconducting energy storage inductor, and dump resistors. The requirements and cost of the power supplies depend on several factors but most critically on the ohmic heating ramp time used for startup. Long ramp times (approx. > 8 s) seems to be feasible, from the standpoint of resistive volt-second losses, and would appear to make conventional systems quite competitive with nonconventional ones, which require further research and development.

The purpose of this Design Guide is to provide additional guidance to aid the DOE facility contractor in meeting the requirement that the siting, design, construction, modification, operation, maintenance, and decommissioning of DOE-owned air-cooled graphite reactors be in accordance with generally uniform standards, guides, and codes which are comparable to those applied to similar reactors licensed by the Nuclear Regulatory Commission (NRC).

The gravity inversion code applies stabilized linear inverse theory to determine the topography of a subsurface density anomaly from Bouguer gravity data. The gravity inversion program consists of four source codes: SEARCH, TREND, INVERT, and AVERAGE. TREND and INVERT are used iteratively to converge on a solution. SEARCH forms the input gravity data files for Nevada Test Site data. AVERAGE performs a covariance analysis on the solution. This document describes the necessary input files and the proper operation of the code. 2 figures, 2 tables.

The cost effectiveness of nonmetallic materials in three direct-use geothermal applications was assessed. An extensive review of the available literature was conducted in order to ascertain those processes for which sufficient design and cost data had been published to permit this economic assessment to be made. Only three such processes could be found and they are discussed.

A major assessment was made of the uranium resources in seawater. Several concepts for moving seawater to recover the uranium were investigated, including pumping the seawater and using natural ocean currents or tides directly. The optimal site chosen was on the southeastern Puerto Rico coast, with the south U.S. Atlantic coast as an alternate. The various processes for extracting uranium from seawater were reviewed, with the adsorption process being the most promising at the present time. Of the possible adsorbents, hydrous titanium oxide was found to have the best properties. A uranium extraction plant was conceptually designed. Of the possible methods for contacting the seawater with the adsorbent, a continuous fluidized bed concept was chosen as most practical for a pumped system. A plant recovering 500 tonnes of U/sub 3/O/sub 8/ per year requires 5900 cubic meters per second of seawater to be pumped through the adsorbent beds for a 70% overall recovery efficiency. Total cost of the plant was estimated to be about $6.2 billion. A computer model for the process was used for parametric sensitivity studies and economic projections. Several design case variations were developed. Other topics addressed were the impact of co-product recovery, environmental considerations, etc.