S>Some recent results from the Los Alamos program in which hydraulic fracturing is used for the recovery of geothermal energy are discussed. The location is about 4 kilometers west and south of the ring fault of the enormous Jemez Caldera in the northcentral part of New Mexico. It is shown that geothermal energy may be extracted from hot rock that does not contain circulating hot water or steam and is relatively impermeable. A fluid is pumped at high pressure into an isolated section of a wellbore. If the well is cased the pipe in this pressurized region is perforated as it is in the petroleum industry, so that the pressure may be applied to the rock, cracking it. A second well is drilled a few hundred feet away from the first. Cold water is injected through the first pipe, circulates through the crack, and hot water returns to the surface through the second pipe. Results are described and circumstances are discussed under which artiflcial geothermal reservoirs might be created in the basaltic rock of Hawaii. (MCW)

Hydraulic fracturing experiments were conducted in granite rock, at temperatures near 100 and 150/sup 0/C, in two wells 0.785 km (2575 ft) and 1.98 km (6500 ft) deep near Los Alamos, New Mexico. No unusual difficulty was observed in fracturing crystalline rock hydraulically. The apparent surface energy (energy required to create new fracture surface by breaking the rock) was measured as 100 J/m/sup 2/. Orientation of the deeper fracture was measured as N35/sup 0/E (+-5/sup 0/). The fraction of fluid injected into the rock that could be recovered at hydrostatic surface pressure was measured. The efficiency of recovery was as high as 92 percent after the fracture impedance was lowered by ''propping'' the fracture with sand. Permeability of the rock over the face of the fracture was compatible with laboratory measurements (10/sup -7/ to 10/sup -8/ darcys). Downhole pressures required to extend the fractures were about 150 and 340 bars (2175 and 4900 psi), respectively.

The Brookhaven National Laboratory Archive and Dissemination System (BNLADS) is designed to deal with the record keeping associated with archiving and disseminating sequential files through a computer network. This data base management system (DBMS) is implemented in a host language that is a subset of PL/I. The stored sequential files that can be dealt with by the BNLADS must be in character mode (ASCII, BCD, EBCDIC). The accessing of fields is specified by a format description which allows for forward processing of fields only. The structure of a case type statement allows for a data field determining a format sequence from a set of format sequences. A data description language (DDL) was devised to describe the accessing sequence of stored sequential files. A data model definition gives the user a view of the content of each stored sequential file. The DDL requires all field type references to contain the field name, so that the BNLADS can access all stored sequential files by logical field name and can write stored sequential files by stating the logical field name without the necessity of referring to formats. The BNLADS is architected in a stratified form in which the application programs are built on …

Design and safety-related construction features of the Hot Fuel Examination Facility/North, located on the Argonne--West site at the Idaho National Engineering Laboratory are described. The proposed operations, the organizational structure, and emergency plans are given. Evaluations of potential accident situations are presented and it is concluded that HFEF/N can be operated safely and without undue hazard.

Division, Dow Chemical U.S.A., for shipping unirradiated fissile material in solid form. Components consist of a 30-gal steel drum, Celotex insulation, and stainless steel containment vessel(s) of 10-in. dia. A simple venting system prevents rtupture of the outer drum in the event of accidental fire. Approved material limits include 5 kg of plutonium or 11 kg of enriched uranium. Thermal decay energy is normally limited to 20 W. Results of extensive tests show the container will function effectively when exposed to all environment and accident conditions as required. The containment vessel temperature rise will not exceed 140 deg F during the thermal test. Internal heating of 20 W will cause an additional temperature rise of 80 deg F. (auth)

The isothermal test series is part of the Semiscale Blowdown and Emergency Core Cooling (ECC) Project conducted by Aerojet Nuclear Company for the U. S. Atomic Energy Commission. The test series consisted of ten blowdown tests and five hot-wall tests with emphasis on emergency core coolant delivery. The blowdown tests were conducted to investigate the effects of lower plenum geometry, heat transfer configuration, ECC injection location, downcomer gap size, and break size.

Physical models for various processes that are encountered in preaccident and transient simulation of thermohydraulic transients in the entire liquid metal fast breeder reactor (LMFBR) plant are described in this report. A computer code, SSC-L, was written as a part of the Super System Code (SSC) development project for the "loop"-type designs of LMFBRs. This code has the self-starting capability, i.e., preaccident or steady-state calculations are performed internally. These results then serve as the starting point for the transient simulation.

Application of a two-phase turbine system to waste heat recovery was examined. Bottoming cycle efficiencies ranging from 15 to 30% were calculated for a 720/sup 0/F diesel exhaust temperature. A single stage demonstration unit, designed for non-toxic fluids (water and DowTherm A) and for atmospheric seals and bearings, had a cycle efficiency of 23%. The net output power was 276 hp at 8,100 rpm, increasing the total shaft power from 1,800 hp for the diesel alone, to 2,076 hp for the combined system. A four stage organic turbine, for the same application, had a rotational speed of 14,700 rpm while a four stage steam turbine had 26,000 rpm. Fabrication drawings were prepared for the turbine and nozzle. The major improvement leading to higher cycle efficiency and lower turbine rpm was found to be the use of a liquid component with lower sensible heat. A reduction in capital cost was found to result from the use of a contact heat exchanger instead of tube-fin construction. The cost for a contact heat exchanger was only $35-52/kWe compared to $98/kWe for a tube-fin heat exchanger. Design drawings and materials list were prepared. A program resulting in the demonstration of a two-phase bottoming system …

The primary objective of the Accident Initiation and Progression Analysis (AIPA) Program is to provide guidance for high-temperature gas-cooled reactor (HTGR) safety research and development. Among the parameters considered in estimating the uncertainties in site boundary doses are uncertainties in fission product source terms generated under normal operating conditions, i.e., fuel body inventories, circulating coolant activity, total plateout activity in the primary circuit, and plateout distributions. The volume presented documents the analyses of these source term uncertainties. The results are used for the detailed consequence evaluations, and they provide the basis for evaluation of fission products important for HTGR maintenance and shielding.

Results are reported from experiments that involved either single or multiple doses of benzo(a)pyrene in mouse skin followed by prolonged observation. Preliminary results indicate linearity in dose and time and no evidence of recovery or enhancement for multiple doses of initiator given for extended periods of time. (auth)

The research proposed here is designed to obtain a better understanding of the temporal kinetics of tumor induction when one or more carcinogens are present simultaneously or sequentially for prolonged periods of time. Studies done to date under this contract have shown that carcinogenesis in mouse skin by polycyclic aromatic hydrocarbon carcinogens is consistent with the induction of dependent and autonomous cell transformations by the carcinogen followed by the conversion of autonomous tumor cells into malignancies at a rate which is determined by the level of carcinogen exposure. Dependent cell transformations remain latent in the skin unless expressed by a promoting agent. Dependent neoplasia appears to follow one-hit kinetics while malignancy is a multihit endpoint. Dose-related and time-related aspects of tumor induction are separable in the initiation-promotion system of mouse skin which along with rat skin and hamster lung is being used as a model for testing hypotheses. Results to date provide the basis for a new interpretation of the linear non-threshold extrapolation model. The broad aim of the study is to provide a basis or rationale for estimating risks associated with prolonged exposures to carcinogens found in the environment and to predict how different tissues and species respond to …

Three generic sheltering/relocation strategies are identified and discussed. They are: population relocation only (no specific sheltering response initiated); sheltering at location following by relocation; and preferential sheltering followed by relocation. Shielding factors representative of these strategies are calculated, and the adequacy of using average shielding factors for the calculation of public health effects is discussed.

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This document presents a common cause failure analysis for Critical LMFBR Shutdown Heat Removal Systems. The report is intended to outline a systematic approach to defining areas with significant potential for common causes of failure, and ultimately provide inputs to the reliability prediction model. A preliminary evaluation of postulatd single initiating causes resulting in multiple failures of LMFBR-SHRS items is presented in Appendix C. This document will be periodically updated to reflect new information and activity.

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.

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A computer program is described which calculates nuclide concentration histories, power or neutron flux histories, burnups, and fission-product birthrates for fueled experimental capsules subjected to neutron irradiations. Seventeen heavy nuclides in the chain from $sup 232$Th to $sup 242$Pu and a user- specified number of fission products are treated. A fourth-order Runge-Kutta calculational method solves the differential equations for nuclide concentrations as a function of time. For a particular problem, a user-specified number of fuel regions may be treated. A fuel region is described by volume, length, and specific irradiation history. A number of initial fuel compositions may be specified for each fuel region. The irradiation history for each fuel region can be divided into time intervals, and a constant power density or a time-dependent neutron flux is specified for each time interval. Also, an independent cross- section set may be selected for each time interval in each irradiation history. The fission-product birthrates for the first composition of each fuel region are summed to give the total fission-product birthrates for the problem.

Whether the wide bandwidth longitudinal feedback system described in this paper is made to act on the individual modes in frequency domain or on the individual bunches in time domain, it represents a clean and efficient way of damping the longitudinal oscillations without influencing other beam parameters such as bunch shape or synchrotron frequency distribution. The frequency domain feedback presents the advantage of providing information on which modes are unstable and on their risetimes, which may be helpful in locating dangerous resonators in the ring.

Calculated results are presented of the photon dose rate from the induced activity produced in the beam stop of a high-energy proton accelerator. Incident proton energies of 400 GeV, 200 GeV, and 30 GeV are considered. In each case the photon dose rate is given as a function of radius in the beam stop and as a function of time after the beam is turned off for assumed operating times of 90 days and 10 years.

A drywell pressurization test was conducted at LLL on February 1, 1977, as part of the NRC /sup 1///sub 5/ scale pressure suppression experiment. A series of four test runs were completed with predicted initial drywell pressurization rates of 14.0, 18.6, 23.0, and 26.0 psi/sec (96.5, 128, 159, and 179 kPa/sec). Each test run consisted of charging various combinations of bottles with nitrogen under high pressure, evacuating the drywell to /sup 1///sub 5/ atmosphere, and opening a valve between the two to allow quick pressurization of the drywell. The pressure-time signatures of all four test runs were in excellent agreement with predicted results made through (1) a computer model developed at LLL and (2) the CONTEMPT-LT computer code which was run by E.G. and G. at the I.N.E.L. Based on the results of the test, only very minor adjustments will be made for the upcoming nitrogen tests with the drywell and toroidal wetwell system linked together.

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.

The annotated bibliography is divided into sections on chemistry and geochemistry, migration and accumulation, cultural distributions, natural distributions, and bibliographies and annual reviews. (LK)

A program to examine the soil-actinide relationship in sediments from a disposal facility was initiated in March 1973. Initial work has been done using samples from the 216-Z-9 covered trench. Soil mounts were made of soil recovered from a core of an uncontaminated well drilled alongside Z-9 trench. The mounts were made by plastic-impregnating smaller, 1-in. diameter cores taken from the original 4-in. diameter cores. The uncontaminated mounts showed that the less than 30 mesh soil was composed of predominately metamorphic rock fragments of the Belt Series, brought down from northern Washington and Idaho by the ancestral Columbia River. Two 4-in. diameter cores, 2 ft in length. were taken from the floor of Z-9 trench. Smaller contaminated mounts were made from these original cores in the same manner as with the uncontaminated samples. Overlying one of these cores (4-- 11), was a sludge layer of silica, alumina and water. The other core (4-5) had no sludge layer. At least two types of plutonium were found in cores 4- 11 and 4- 5 by autoradiographic and microprobe examination. The plutonium particles (up to 10 mu m in diameter and 60 wt% PuO/sub 2/) were the most conspicuous form. These occurred near …