The rate constant for electron attachment to F{sub 2} was measured at 233 to 373 K in nitrogen at 0.04--0.75 eV and in argon at 298 K at 0.4--2.95 eV. The unfolded cross section was compared with calculations. The ionization threshold of N,N,N{prime},N{prime}-tetramethyl-p-phenylenediamine (TMPD) was measured in ethane over the density range 0.15--13.3 M/l at 295--413 K using multiphoton ionization conductivity.

Integral to the design of an accelerator facility is the provision of adequate shielding to contain any radiation arising from operation of the facility. Complementary to the questions of environmental shielding are a number of radiation questions related to operation of the completed facility. One obvious need is the specification of systems for monitoring environmental emissions to ensure consistency between the design criteria and the actual levels during operation. Another question is the effect on the components of the machine of the radiation within the environmental shield. These questions were examined at the workshop. This report is a summary of the materials presented at the workshop.

The measurement of the risk-related impacts from the siting of a high-level nuclear waste (HLNW) repository represents a new and important addition to conventional socioeconomic impact studies. In particular, the driving forces behind these impacts are the risks people perceive to be associated with the repository. Measuring the risk impacts requires a complementary set of approaches, of which, risk surveys are the cornerstone.a The purpose of these surveys is to provide scientifically defensible measures of the risk-related impacts. The risk surveys follow directly from a conceptual framework of how the HLNW repository affects peoples` perceptions and, ultimately, their behaviors. These surveys describe and measure: Characteristics of individuals, Risks people perceive from the HLNW repository, Views, or mind sets, they form about the HLNW repository, Changes in behaviors--e.g., changes in retirement decisions or industrial relocations--induced by the location of the repository, and Changes in well-being of Nevada citizens, if the repository were located at Yucca Mountain.

The environmental radiation shielding requirements of the SSC have been evaluated using currently available computational tools that incorporate the well known processes of energy loss and degradation of high energy particles into Monte Carlo computer codes. These tools permit determination of isodose contours in the matter surrounding a source point and therefore the specification of minimum thicknesses or extents of shielding in order to assure annual dose equivalents less than some specified design amount. For the general public the annual dose equivalent specified in the design is 10 millirem, small compared to the dose from naturally occurring radiation. The types of radiation fall into two classes for the purposes of shielding determinations-hadrons and muons. The sources of radiation at the SSC of concern for the surrounding environment are the interaction regions, the specially designed beam dumps into which the beams are dumped from time to time, and beam clean-up regions where stops remove the beam halo in order to reduce experimental backgrounds. A final, unlikely source of radiation considered is the accidental loss of the full beam at some point around the ring. Conservative choices of a luminosity of 10{sup 34} cm{sup {minus}2}s{sup {minus}1} and a beam current three times …

The CERN Intersecting Storage Rings (ISR) operated from 1971 to 1984. During that time high-energy physics experiments were carried out with 30 GeV colliding proton beams. At the end of this period the machine was decommissioned and dismantled. This involved the movement of about 1000 machine elements, e.g., magnets, vacuum pumps, rf cavities, etc., 2500 racks, 7000 shielding blocks, 3500 km of cables and 7 km of beam piping. All these items were considered to be radioactive until the contrary was proven. They were then sorted, either for storage and reuse or for radioactive or non-radioactive waste. The paper describes the radiation protection surveillance of this project which lasted for five months. It includes the radiation protection standards, the control of personnel and materials, typical radioactivity levels and isotopes, as well as final cleaning and decommissioning of an originally restricted radiation area to a free accessible area.

This progress report presents information on a number of different projects worked on during the reporting period. One project is the design and performance of a multiplicity jump trigger. The prototype consist of an upstream interaction veto detector, a 3/16 inch long graphite target, a pair of before multiplicity detectors, a 1 inch decay region, and finally six after multiplicity detectors. All detectors were 300 micron thick silicon wafers with a 14 mm square active area. A tritium proportional chamber was built to check Simpson`s result regarding evidence for a 17 keV massive neutrino seen in tritium decay. An electrostatic beta spectrograph has been constructed over the past five years. This detector will use hemispherical electrostatic fields to decelerate electrons from tritium beta decay. Integral endpoint spectra will be measured. The objective is to measure the electron antineutrino mass. A wide ranging theoretical program on non-perturbative quantum field theory work has been ongoing. The calculations which are being worked on involve both the electroweak and the strong interactions. In addition research work on a beam drift chamber, beam solid state detectors, and time-of-flight system are reviewed. A resistive plastic, proportional tube, gas hadron calorimeter with pad readout is described. Also …

Estimates have been made of the residual radioactivation of the components of the SSC accelerator and detector complex. Such activation is caused by the loss of a small fraction of the proton beams being transported in the SSC accelerator system, by deliberate removal (dumping) of the beams and by particles created in the proton-proton collisions in the SSC storage rings. Existing methodology that has been successfully used to determine activation levels at other accelerator facilities has also been used to estimate the activation of SSC components in those cases where calculational methods may be applied. In addition, we have used measurements from existing accelerators, primarily the Fermilab and CERN accelerators, to provide the means to estimate activation for those cases in which calculational methods, such as Monte Carlo shower codes, are difficult to apply. We have also used these measurements to check the calculations from the shower codes where possible. We have estimated activation levels and dose rates, where possible, for the following components of the SSC: The abort dumps for both the storage rings and the elements of the injector system; beam Collimators and scrapers; magnets and other apparatus in the region of injection/extraction from one accelerator to another, …

Geological and geophysical evidence supports the existence of extensional detachments, between the Sheep Range and Death Valley. It is proposed that geographically separated pieces of detachments between Death Valley and the Sheep Range are parts of a regional detachment system that has evolved since the Miocene, and that the system consists of lenses of strata separated by an anastomosing network of low- and high-angle normal faults. This manuscript emphasizes the probability that isostatic uplift within the region of greatest crustal attenuation in this system, the Bullfrog Hills core complex, controlled the evolution of the detachment system between the breakaway zone a the Sheep Range and the core complex. Features in this system are described from east to west, which is the apparent direction of tectonic transport.

The Task Force on Collision Hall Limitations met March 23--26, 1987, to obtain a greater understanding of the civil construction requirements for a large scale model SSC detector and to identify limitations, if any, on overall detector scale and individual detector components that may result from civil construction limitations. To this purpose the Task Force studied civil construction techniques and limitations for both deep sites and surface or near surface sites, developed limits and criteria for model detector assembly and servicing, developed a model detector assembly scenario, and estimated an overall schedule from initiation of the design of the experimental hall complex to the completion of the assembly of the model detector. Our conclusions apply only to facilities required to house experiments of the scale of the model detector studied. From our studies it is apparent that the experimental hall complex required for SSC-scale detectors can be constructed under a variety of assumptions regarding the eventual SSC site. There may be significant differences in the schedule and the cost of the experimental hall complex between surface and deep underground locations, with the deep underground, in general, being more expensive and requiring a longer time for construction. The difference in cost …

A preliminary survey of aerial photographs of the southern Walker Lane began in late 1986. The purpose of this survey is to determine the nature and scope of future studies required to ascertain whether the apparent concentration of Quaternary faults in and near the Nevada Test Site is real or is simply a result of the greater effort invested in mapping Quaternary deposits in that area, and determine whether faults in the southern Walker Lane are active and could produce significant earthquakes. The survey is focused on the area extending south from Lone Mountain to Pahrump Valley and east from the Furnace Creek fault zone to an irregular line passing through the Cactus Range and Pahute Mesa. Lineaments and scraps were identified on stereopairs of black-and-white aerial photographs at scales of 1:80,000 or 1:60,000. The lineaments and and scarps were plotted on 1:24,000- and 1:62,500-scale topographic maps using a PG-2 plotter, and were color-coded according to distinctness and occurrence in Quaternary or Tertiary deposits (age assignments based on appearance in aerial photographs and on existing geologic maps). Additional lineaments identified on the topographic maps were also plotted. Areas of particular interest were selected for more detailed study using larger-scale aerial …

This report was prepared to provide an introduction into understanding the characteristics, including economics, of photovotaically powered water pumping systems

Reference repository concepts designs adopted by domestic and foreign waste disposal programs are reviewed. Designs fall into three basic categories: deep borehole from the surface; disposal in boreholes drilled from underground excavations; and disposal in horizontal tunnels or drifts. The repository concepts developed in Sweden, Switzerland, Finland, Canada, France, Japan, United Kingdom, Belgium, Italy, Holland, Denmark, West Germany and the United States are described. 140 refs., 315 figs., 19 tabs.

The Western Area Power Administration has established an effective formal environmental protection, auditing, and monitoring program which has been in effect since 1978. This annual site environmental report discusses the significant environmental projects and issues Western was involved with in 1986, and it is written to demonstrate the nature and effectiveness of the environmental protection program. Western has numerous facilities located in 15 states. This report was written to address all the facilities.

This Safety Analysis Report for Packaging (SARP) satisfies the request of the US Department of Energy for a formal safety analysis of the shipping container identified as USA/9507/BLF, also called AL-M1, configuration 5. This report makes available to all potential users the technical information and the limits pertinent to the construction and use of the shipping containers. It includes discussions of structural integrity, thermal resistance, radiation shielding and radiological safety, nuclear criticality safety, and quality control. A complete physical and technical description of the package is presented. The package consists of an inner container centered within an insulated steel drum. The configuration-5 package contains tritiated water held on sorbent material. There are two other AL-M1 packages, designated configurations 1 and 3. These use the same insulated outer drum, but licensing of these containers will not be addressed in this SARP. Design and development considerations, the tests and evaluations required to prove the ability of the container to withstand normal transportation conditions, and the sequence of four hypothetical accident conditions (free drop, puncture, thermal, and water immersion) are discussed. Tables, graphs, dimensional sketches, photographs, technical references, loading and shipping procedures, Monsanto Research Corporation-Mound experience in using the containers, and a copy …

This report deals with the second-year (1985-86) findings of an on going experiment with winter wheat (Triticum aestivum L.) at different carbon dioxide (CO{sub 2}) levels and under two moisture regimes. The results for the first year are given in the U.S. Department of Energy, Carbon Dioxide Research Division Response of Vegetation to Carbon Dioxide. The purpose of the second year`s experiment was to verify the results of 1984-85. However, based on the performance and the results of 1984-85 experiments, a few modifications were made.

The following report marks the third quarter of the third phase of the centrifugal slurry pump improvement program. The program was begun in 1982 for the purpose of improving the operating life of centrifugal slurry pumps for coal liquefaction service. This phase of work will verify the design of a pump at higher speed operation. Eventual scale-up of the prototype slurry pumps to full-scale synthetic fuel generation plants could require ten times the flow. The higher speed will allow pumps to be smaller with respectable efficiencies. Conversely, without increasing the specific speed of the pump design, the eventual size would be more than triple that of the prototype slurry pump. The prototype slurry pump during this phase of the program incorporated all the features proven in the earlier phases of the program. This new, higher specific speed pump will be tested for the ability of the hydraulic design to inhibit wear. It will be tested and compared to the previous optimum prototype slurry pump of this program.

This report covers the third quarter of the third phase of the reciprocating charge pump improvement program. The program was begun in 1982 for the purpose of improving the operating life of packings and plungers used in 300 psig, 300F coal/solvent slurry pumps employed in synthetic fuel generating plants. The testing to be performed during this phase has been modified since the last quarterly report. This test measured the effects of slurry migration past the floating piston seal and the time to wear the packing and plunger beyond the acceptable limit. Table 1 summarizes all testing to date, 456 hours total at this time with 72 hours on 35% slurry. It denotes the valve problems seen with rapid pressure decay when pumping slurry. Throughout this time, 33 specific and different equipment failures and operation problems occurred that delayed the testing.

Core bore samples were obtained from the severely damaged TMI-2 core during July and August, 1986. A description of the TMI-2 core bore drilling unit used to obtain samples; a summary and discussion of the data from the ten core bore segments which were obtained; and the initial results of analysis and evaluation of these data are presented in this report. The impact of the major findings relative to our understanding of the accident scenario is also discussed.

This report marks the fourth quarter of the third phase of the centrifugal slurry pump improvement program. The program was begun in 1982 to improve the operating life of centrifugal slurry pumps for coal liquefaction service. The first phase reviewed pilot plant experience with centrifugal slurry pumps and identified, with the help of a literature search, the critical design parameters and materials required for such improvement. The second phase encompassed extensive small-scale testing of several hydraulic design concepts and materials testing and selection - the results being incorporated in a prototype slurry pump design. This third phase of the work has included i) prototype slurry pump testing against a state-of-the-art coal liquefaction slurry pump, wherein substantial reduction of wear was obtained at 60% higher speed at the same head and flow rate therefore at 60% higher specific speed - and ii) an investigation as to whether still higher specific speed is possible. The prototype pump tested in (i) had a specific speed of 600. Another pump of this same design was re-fitted for investigation (ii) with a smaller impeller and associated liners so as to operate at a specific speed of 1000. Both the 600 and the 1000 impellers for …

1986 was another year of major advances for SSRL as the ultimate capabilities of PEP as a synchrotron radiation source became more apparent and a second PEP beam line was initiated, while effective development and utilization of SPEAR proceeded. Given these various PEP developments, SSRL abandoned its plans for a separate diffraction limited ring, as they abandoned their plans for a 6--7 GeV ring of the APS type last year. It has become increasingly apparent that SSRL should concentrate on developing SPEAR and PEP as synchrotron radiation sources. Consequently, initial planning for a 3 GeV booster synchrotron injector for SPEAR was performed in 1986, with a proposal to the Department of Energy resulting. As described in Chapter 2, the New Rings Group and the Machine Physics Group were combined into one Accelerator Physics Group. This group is focusing mainly on the improvement of SPEAR`s operating conditions and on planning for the conversion of PEP into a fourth generation x-ray source. Considerable emphasis is also being given to the training of accelerator physics graduate students. At the same time, several improvements of SSRL`s existing facilities were made. These are described in Chapter 3. Chapter 4 describes new SSRL beam lines being …

This revised Safety Analysis Report for Packaging (SARP) satisfies the requirement of the US Department of Energy (DOE) for an updated formal safety analysis of the two insulated drum shipping containers identified as USA/5790/BLF and USA/5791/BLF. The report makes available to all potential users the technical information and limits pertinent to the construction and use of the shipping containers. This SARP includes discussions of structural integrity, thermal resistance, radiation shielding and radiological safety, nuclear criticality safety, and quality control. Complete physical and technical descriptions of the packages are presented. Each package consists of a cylindrical steel inner container centered within an insulating steel drum assembly. The contents may be any radioactive materials that satisfy the requirements established in this SARP. A shipment of plutonium-238 in the form of a solid oxide is evaluated in this SARP as an example. Design and development considerations, the tests and evaluations required to prove the ability of the containers to withstand normal transportation conditions, and the sequence of four hypothetical accident conditions (free drop, puncture, thermal, and water immersion) are discussed. Tables, graphs, dimensional sketches, photographs, technical references, loading and shipping procedures, Mound Facility experience in using the containers, and copies of the DOE …

This Report is a presentation of time versus concentration plots for results of the groundwater monitoring program conducted by the Health Protection Department. This purpose of this report is to provide a tool for interpretation of the groundwater at the sites monitored. It should be used in conjunction with the U.S. Department of Energy Savannah River Plant Environmental Report for 1984 (DPSPU-86-30-1), the U.S. Department of Energy Savannah River Plant Environmental Report for 1986 (DPSPU-86-30-1), and the quarterly reports of the groundwater monitoring program for the first two quarters of 1987 (HPR-87-158 and HPR-87-286)

This report assesses the possible options for retention of tritium and its ultimate disposal during future reprocessing of irradiated oxide fuels discharged from light water reactors (LWRs) and liquid metal fast breeder reactors (LMFBRs). The assessment includes an appraisal of the state of the retention and disposal options, an estimate of the dose commitments to the general public, an estimation of the incremental costs of the several retention and disposal options, and the potential reduction of the dose commitments resulting from retention and disposal of the tritium. The assessment is based upon an extensive study of tritium retention in reprocessing completed in 1982 by Grimes et al. Two plants were assumed, one to process LWR oxide fuel and the other to process LMFBR fuel. In each base case plant the tritium was vaporized to the atmosphere. Each of the hypothetical plants was assumed to be constructed during the 1990`s and to operate for a 20-year lifetime beginning in the year 2000 at a rate of 1,500 metric tons of heavy metal (MTHM) per 300-d year. In addition to the base case (Case 1), six other cases which included tritium retention options were examined. Although many of the features of the …

The Fission Gas Plenum Experiment was conducted at the Oak Ridge National Laboratory Tower Shielding Facility during FY 1987 to: provide data for verification of the assumptions and calculational methods used to determine the neutron leakage from the plenum, and provide an uncertainty evaluation associated with the calculations. The Tower Shielding Reactor source was modified to represent the neutron spectrum leaving a typical liquid-metal-cooled reactor core along its axis. The experimental configurations resulted from the insertion of either a homogeneous or homogeneous-heterogeneous gas plenum combination into the iris of a concrete slab, with the only variable being the thickness of the plenum. Integral neutron fluxes were measured behind each of the configurations at specified locations, and neutron spectra were obtained behind selected mockups. The experimental data are presented in both tabular and graphical form. This experiment is the second in a series of six experiments to be performed as part of a cooperative effort between the United States Department of Energy and the Japan Power Reactor and Nuclear Fuel Development Corporation. The research program is intended to provide support for the development of advanced sodium-cooled reactors.