This report describes the design of a magnetic spectrometer facility to be built in the Tagged Photon Lab. The design has been developed by a collaboration of physicists from Fermilab, The University of California at Santa Barbara, The University of Colorado and The University of Toronto. This group was formed to build the facility and to carry out the experiment described in Proposal 516, which is a study of photoproduced states (including charm and hidden charm) with a forward mass > 2.5 GeV. Although the design of the facility is developed from that outlined in P-516, much thought has gone into making the facility versatile enough to be used for a continuing program of physics by different groups. In addition to the 100 GeV photon physics of P-516, this facility is designed to be useful for experiments like the following: pion production experiments, hadron jet experiments, {ge} 300 GeV and very high intensity photon physics with the energy doubler including searches for and studies of heavy leptons. The report goes into a detailed description of the various detectors which will be part of this detector system, and the experimental equipment which will be built. Sections of this report give detailed …

The transcript of the Scoping Meeting for preparation of the Environmental Impact Statement for the Durango uranium mill tailings project is presented.

The purpose of this Public Participation Plan is to explain the Department of Energy`s plan for involving the public in the decision-making process related to the Uranium Mill Tailings Remedial Action (UMTRA) Project. This project was authorized by Congress in the Uranium Mill Tailings Radiation Control Act of 1978. The Act provides for a cooperative effort with affected states and Indian tribes for the eventual cleanup of abandoned or inactive uranium mill tailings sites, which are located in nine western states and in Pennsylvania. Section 111 of the Act states, ``in carrying out the provisions of this title, including the designation of processing sites, establishing priorities for such sites, the selection of remedial actions and the execution of cooperative agreements, the Secretary (of Energy), the Administrator (of the Environmental Protection Agency), and the (Nuclear Regulatory) Commission shall encourage public participation and, where appropriate, the Secretary shall hold public hearings relative to such matters in the States where processing sites and disposal sites are located.`` The objective of this document is to show when, where, and how the public will be involved in this project.

This paper summarizes the recent letdown and block valve experience in the liquefaction pilot plants. Also included is a brief description of the research and development activities on valves which are conducted in supporting laboratories. The purpose of the summary is to concentrate on critical component problems common to all liquefaction plants, to avoid duplication of efforts, and to help provide timely solutions to the valve problems. The main source of information used in this paper is the Minutes of the Critical Component and Materials Meeting which is sponsored by the Office of Coal Processing, Fossil Energy, Department of Energy. Other sources of information such as the technical progress reports are also included based on availability and relevance to topics covered in this paper. It is intended that this report will be followed by updates as pertinent information concerning valves becomes available. In the subsequent sections of this paper a brief outline of past valve studies is given as background material followed by a summary of the most recent valve operating experience at the liquefaction plants.

The MC3642 is a dual channel thermal battery used on the DE1010/W85 Command Disable Controller. It utilizes the CalCaCrO{sub 4} electrochemical system. The electrical requirements of this battery are as follows: RISE TIME PEAK VOLTAGE ACTIVE LIFE LOAD Channel 1 - 1.0 Sec. Max. 34 Volts 10 Sec. Min. 40.0 Ohms to 20 Volts above 20 Volts Channel 2 - .350 Sec. Max. 42 Volts 10 MSec. Min. 6.5 Ohms to 23 Volts above 23 Volts The battery consists of 14 cells connected in series (Channel 2) and 12 cells connected in series (Channel 1). Each cell is composed of an anode fabricated from a bimetallic sheet (0.005{double_prime} thick calcium on 0.005{double_prime} thick iron substrate), a depolarizer-electrolyte-binder (DEB) pellet and a heat pellet. Activation is achieved by mechanical primer. Optimum battery performance is achieved with a 35155/10 DEB pellet weighing .80g and a heat pellet, weighing 1.30 grams, of 88/12 heat powder.

To obtain the data necessary for evaluating the nuclear design method of a large-scale fast breeder reactor, criticality tests with a large- scale homogeneous reactor were conducted as part of a joint research program by Japan and the U.S. Analyses of the tests are underway in both countries. The purpose of this paper is to describe the status of this project.

Sorption of americium and plutonium was measured in a controlled, oxygen-free atmosphere and in air on a series of tuff samples. Sorption of plutonium was greater in the controlled atmosphere than in air. Sorption of both elements is higher on zeolitized tuff than devitrified tuff. Sorption of strontium, cesium, barium, cerium, and europium is being measured on tuff samples of mineralogies not previously studied, and samples from the USW-G1 drill hole have been selected for study. Work on the dependence of the sorption ratio on element concentration (barium and europium) and on solution-to-solid ratios is reported. Progress on controlling Eh and making Eh measurements is presented. Some tuff-water systems exhibit reduced or negative Eh values under oxygen-free conditions. Development of a method for encasing cores for flow studies is discussed. Field geologic mapping is being conducted in the Lunar Crater volcanic field of central Nevada. Mineralogy-petrology studies are being conducted on core samples from the USW-G1 exploration hole in Yucca Mountain. Zeolite heating tests of core samples from UE25a-1 show density, volume, and weight changes that correlate with alteration of mineral assemblages. Hydrogen-deuterium ratios in water evolved from a clinoptilolite specimen from Yucca Mountain have been measured. Jacket seals leaked …

Silicic tuffs of the southern Great Basin and basalts of the Columbia River Plateau are under investigation as potential host rocks for high- and intermediate-level radioactive wastes. Nonwelded and partially welded tuffs may contain major amounts (> 50%) of the zeolite minerals clinoptilolite, mordenite, and analcime. Densely welded tuffs and some basalt flows may contain clinoptilolite as fracture filling that limits the permeability of these rocks. The cation exchange properties of these zeolite minerals allow them to pose a formidable natural barrier to the migration of cationic species of various radionuclides in aqueous solutions. However, these minerals are unstable at elevated temperatures and at low water-vapor pressures and may break down either by reversible dehydration or by irreversible mineralogical reactions. All the breakdown reactions occurring at increased temperature involve a net volume reduction and evolution of fluids. Thus, they may provide a pathway (shrinkage fractures) and a driving force (fluid pressure) for release of radionuclides to the biosphere. These reactions may be avoided by keeping zeolite-bearing horizons saturated with water and below about 85{sup 0}C. This may restrict allowable gross thermal loadings in waste repositories in volcanic rocks.

The detailed mineralogy of the Bullfrog and Tram Members of the Crater Flat Tuff from drill hole USW-G1 has been examined, primarily to characterize fully the amounts and types of clay minerals in the tuffs and the possible effects clay minerals have on rock properties. Results of bulk sample x-ray diffraction analyses agree closely with previous determinations, although slightly higher clay mineral contents were found in this study. X-ray diffraction analysis of fine fractions revealed that the clay minerals in the tuffs are sodium-saturated montmorillonite-beidellites with typical layer charges and no high-charge layers. These smectites are found in virtually all samples of the Bullfrog and Tram, and there is no correlation between the amounts of smectites and the amounts of zeolite, quartz, and feldspar. Smectites are present in both welded and nonwelded horizons and are scarce in some zones with slight-to-absent welding.

This report is divided into the following sections: (1) facility reports (Argus and Shiva); (2) Nova project; and (3) fusion experiments. In the Fusion Experiments section of this report, the author describes the results of a series of experiments on Shiva which further the understanding of the production and transport of suprathermal electrons. He found that of the suprathermal electrons which strike a laser irradiated disk target or which interact with the rear surface of a half Cairn hohlraum target, a significant fraction of these electrons orbit the target and strike the rear of the disk. These results have significant implications in the interpretation and modeling of the laser irradiated target experiments.

This report describes the following investigations being pursued under photovoltaic technology development at Sandia National Laboratories: photovoltaic systems technology; concentrator technology; concentrator arrays and tracking structures; concentrator solar cell development; system engineering; subsystem development; and test and applications.

Basic concepts for using the energy of the sun have been known for centuries. The challenge today, the goal of the Department of Energy`s National Solar Energy Program is to create the technology needed to establish solar energy as a practical, economical alternative to energy produced by depletable fuels--and to use that solar-produced energy in a wide variety of applications. To assist the DOE in this national effort, Sandia sponsors industrial and university research and development, manages a series of technical programs, operates solar experimental facilities, and carries out its own scientific and engineering research. This booklet describes their projects, their technical objectives, and explains how their experimental facilities are used to find the answers we`re seeking. Prospective participants from companies involved in solar-energy development or applications should find it especially useful since it outlines broad areas of opportunity. Projects include: central receiver technology; line-focus thermal technology; photovoltaic systems technology; wind turbine development; energy storage technology; and applied research in improved polycrystalline materials for solar cells and photoelectrolysis of water.

After the Farm event, gages measuring horizontal accelerations at the bottom of Well J-11 began resonating at about 3 to 5 hertz on each shot. This investigation of possible causes concludes that the material surrounding the well casing has fallen away, allowing the casing to move freely in horizontal directions and causing the undesirable resonance.

Tuffs of the Nevada Test Site are currently under investigation to determine their potential for long-term storage of radioactive waste. As part of this program, hole USW-G1 was drilled to a depth of 6000 ft below the surface, in the central part of the Yucca Mountain area, Nevada Test Site, Nevada. Petrographic study of the USW-G1 core is presented in this report and shows the tuffs (which generally were variably welded ash flows) are partly recrystallized to a variety of secondary minerals. The important alteration products are zeolites (heulandite, clinoptilolite, mordenite and analcime), smectite clays with minor interstratified illite, albite, micas, potassium feldspar, and various forms of silica. Iijima`s zeolite zones I through IV of burial metamorphism can be recognized in the core. Zeolites are first observed at about the 1300-ft depth, and the high-temperature boundary of zeolite stability in this core occurs at about 4350 ft. Analcime persists, either metastably or as a retrograde mineral, deeper in the core. The oxidation state of Fe-Ti oxide minerals, through most of the core, increases as the degree of welding decreases, but towards the bottom of the hole, reducing conditions generally prevail. Four stratigraphic units transected by the core may be potentially …

This document is a report of activities performed by Westinghouse Advanced Energy Systems Division-Nevada Operations at the E-MAD Facility, Area 25, Nevada Test Site, in meeting subtask objectives during the second quarter of Fiscal Year 1981. These activities include: transfer of the Fuel Temperature Test (FTT) assembly from the West Process Cell to the Hot Bay where it was disassembled; boiling water calorimetry, Weld Pit calorimetry, encapsulation, and temporary storage of the fuel assembly used in the FTT; completion of the first Climax Test fuel exchange; testing to evaluate moisture accumulation in Drywells; Plasma Arc Welder development; receipt, installation, and activation of the Remote Area Monitoring (RAM)/(CAM) system and alpha/beta/gamma counting system.

Storage of radwaste in tuff was studied. Adsorption experiments were conducted with {sup 85}Sr, {sup 95}Tc, {sup 137}Cs, {sup 133}Ba, and {sup 152}Eu. The geochemistry and mineralogy-petrology of tuff were studied. Organic and inorganic Eh buffers were investigated. Rock physics studies were also conducted. (DLC)

A generic test of the geologic storage of spent-fuel assemblies from an operating nuclear reactor is being made by the Lawrence Livermore National Laboratory at the US Department of Energy`s Nevada Test Site. The spent-fuel assemblies were emplaced at a depth of 420 m (1370 ft) below the surface in a typical granite and will be retrieved at a later time. The early time, close-in thermal history of this type of repository is being simulated with spent-fuel and electrically heated canisters in a central drift, with auxiliary heaters in two parallel side drifts. Prior to emplacement of the spent-fuel canisters, preliminary calculations were made using a pair of existing finite-element codes. Calculational modeling of a spent-fuel repository requires a code with a multiple capability. The effects of both the mining operation and the thermal load on the existing stress fields and the resultant displacements of the rock around the repository must be calculated. The thermal loading for each point in the rock is affected by heat tranfer through conduction, radiation, and normal convection, as well as by ventilation of the drifts. Both the ADINA stress code and the compatible ADINAT heat-flow code were used to perform the calculations because they …

Recent (1977 to 1978) gravity and aeromagnetic surveys of the Timber Mountain region, southern Nevada, have revealed new details of subsurface structure and lithology. The data strongly suggest that deformation caused by volcanic events has been accommodated along straight-line faults combining in such a fashion as to given a curvilinear appearance to regional structure. The magnetic data suggest that rock units in the central graben and along the southeast margin of Timber Mountain may have been altered, perhaps thermally, from their original state. The gravity data indicate that the south part of the Timber Mountain is underlain by relatively dense rock possibly intrusive rock, like that which crops out along its southeast side. The gravity data also suggest that the Silent Canyon caldera may extend considerably south of its presently indicated southern limit and may underlie much of the area of Timber Mountain. The moat areas appear to be more rectangular or triangular than annular in shape. The southern part of Timber Mountain caldera is separated from the Yucca Mountain area to the south by a triangular horst. The structural relations of the rock units making up the horst are complex. Several linear terrain features in the southern part of …

This report is the third in a series of reports describing studies of sorption and migration of radionuclides in tuff. The investigations were extended to lithologies of tuff not previously studied. Continuing experiments with uranium, plutonium, and americium are described. The dependence of sorption on the concentration of the sorbing element and on the solution-to-solid ratio was investigated for a number of nuclides and two lithologies. A circulating system was designed for measuring sorption ratios. Values obtained from this system, batch measurements, and column elutions are compared. Progress on measuring and controlling Eh is described.

Measurements of thermal conductivity, thermal diffusivity, and thermal linear expansion have been made on two rock types, a rock salt and a quartz monzonite, at temperatures from 300 to 573{sup 0}K and confining pressures from 10 to 50 MPa. The samples were taken from deep rock formations under consideration as possible sites for a nuclear waste repository - the rock salt from a domal salt formation at Avery Island, Louisiana, and the quartz monzonite from the Climax Stock, Nevada Test Site, Nevada. The testing temperature and pressures are meant to bracket conditions expected in the repository. In both rock types, the thermal properties show a strong dependence upon temperature and a weak or non-dependence upon confining pressure. Thermal conductivity and diffusivity both decrease with increasing temperature in approximately linear fashion for samples which have not been previously heated. At 50 MPa in both rocks this decrease closely matches the measured or expected intrinsic (crack-free) behavior of the material. Preliminary indications from the quartz monzonite suggest that conductivity and diffusivity at low pressure and temperature may decrease as a result of heat treatment above 400{sup 0}K.

The mined geologic burial of high level nuclear waste is now the favored option for disposal. The US National Waste Terminal Storage Program designed to achieve this disposal includes an extensive rock mechanics component related to the design of the wastes repositories. The plan currently considers five candidate rock types. This paper deals with the three hard rocks among them: basalt, granite, and tuff. Their behavior is governed by geological discontinuities. Salt and shale, which exhibit behavior closer to that of a continuum, are not considered here. This paper discusses both the generic rock mechanics R and D, which are required for repository design, as well as examples of projects related to hard rock waste storage. The examples include programs in basalt (Hanford/Washington), in granitic rocks (Climax/Nevada Test Site, Idaho Springs/Colorado, Pinawa/Canada, Oracle/Arizona, and Stripa/Sweden), and in tuff (Nevada Test Site).

This progress report covers dosimetry work at the Climax Spent Fuel Test Facility up to September 1981. During this time the gamma calibrations were completed, the temperature-induced fading study was completed, the first set of exposed dosimeters was retrieved, and the second set of dosimeters was placed in the field. These were installed in stainless steel tubes located on the inside wall of five canister emplacement holes (0.61 m in diameter), numbers 1, 3, 4, 7, and 11. Hole 3 also had dosimeters in similar stainless steel tubes placed at radii of 0.51 and 0.66 m from the canister centerline. Data obtained from the first exposure (about 270 days in duration) are reported. Significant neutron exposures were measured; in some cases they were sufficiently high that neutron spectra could be calculated.

When considering groundwater flow and radionuclide retention in the complex flow systems that can occur in geologic formations, one has a serious problem in determining if laboratory studies are being performed under conditions appropriate to natural systems. This document is the project plan for a program designed to begin to address these problems. The project is being carried out jointly by the Los Alamos National Laboratory, Sandia National Laboratories, and Argonne National Laboratory. The work has three principal objectives: (1) to develop the experimental, instrumental, and safety techniques necessary to conduct controlled, small-scale radionuclide migration field experiments, including those involving actinides; (2) to use these techniques to define radionuclide migration through rock by performing generic, at-depth experiments under closely monitored conditions; and (3) to determine whether available lithologic, geochemical, and hydrologic properties together with existing or developing transport models are sufficient and appropriate to describe real field conditions.

Measurements of thermal conductivity and thermal diffusivity have been made on two samples of Climax Stock quartz monzonite at pressures between 3 and 50 MPa and temperatures between 300 and 523{sup 0}K. Following those measurements the apparatus was calibrated with respect to the thermal conductivity measurement using a reference standard of fused silica. Corrected thermal conductivity of the rock indicates a value at room temperature of 2.60 +- 0.25 W/mK at 3 MPa increasing linearly to 2.75 +- 0.25 W/mK at 50 MPa. These values are unchanged (+- 0.07 W/mK) by heating under 50-MPa pressure to as high as 473{sup 0}K. The conductivity under 50-MPa confining pressure falls smoothly from 2.75 +- 0.25 W/mK at 313{sup 0}K to 2.15 +- 0.25 W/mK at 473{sup 0}K. Thermal diffusivity at 300{sup 0}K was found to be 1.2 +- 0.4 X 10{sup -6} m{sup 2}/s and shows approximately the same pressure and temperature dependencies as the thermal conductivity.