Even though peripheral heavy-ion collisions are less violent than their central counterparts, the large energy exchange between the reactants often leaves the primary products in excited particle-unstable states whose subsequent decay leads to 3 or more nuclei emerging in the final exit channel. These post-reaction, predominantly sequential de-excitation processes can sometimes provide interesting structural information about the parent nuclei. In fact, provided these processes are well understood, one can employ them as probes for studying initial properties of the fragments. This report discusses results of two experiments that deal with (1) nonstatistical, rare decay modes of the projectile, and (2) internal excitation energy of the projectile- and target-like fragments in peripheral collisions. The physics addressed in each is different, but the experimental and data-analysis techniques are so similar that it is relevant to join them together.

Experimental data for fragmentation in the reactions /sup 93/Nb = /sup 9/Be, /sup 12/C, and /sup 27/Al are presented. Data were obtained from the LBL BEVALAC (25 to 40 MeV/u), GSI Unilac (11 to 18 MeV/u) and LBL SuperHILAC. These measurements imply, that over a large range of bombarding energies, intermediate mass fragments are produced by the bineary decay of a compound nucleus-like system. At low bombarding energies, these systems are associated with a complete fusion reaction, whereas for the larger energies the initial system is formed in an incomplete fusion reaction. The data shows a smooth evolution from the lower energies, where the statistical emission of intermediate mass fragments is well established, to the higher, intermediate energy regime. 4 refs., 2 figs.

The feasibility of a biological facility to treat geothermal sludge from a base case 50-MW double-flash geothermal power plant in the Imperial Valley, California was evaluated. The effect of sludge and nutrient concentration, agitation air bubbling and sterility on the rate of metal solubilization by the bacteria Thiobacillus thiooxidans and ferrooxidans was examined. All experiments were performed in batch flasks and monitored daily for bacterial growth. T. Thiooxidans leached 36% of the zinc in the sludge after 288 hr but leached little chromium. T. ferrooxidans removed 60% of the chromium in the sludge after 250 hr but did not leach zinc. Sludge to medium ratios of greater than 10% were toxic to the microorganisms studied. the experimental results were used to design a biological solid-waste treatment plant. The design basis used was 5 wt % sludge in the leaching vessel with a residence time of 10 days. The non-regulated waste resulting from the treatment plant could be used for land fill or construction materials. The total capital cost for the bio-leaching plant is $3.3 million with an annual operating cost of $690,000. The total cost of this plant is about 0.2 cents/kWh of electricity produced, which is essentially the same …

The purpose was to evaluate enhancement methodologies that can be used to rebuild runs of spring chinook salmon in the Yakima River basin. The objectives were to: (1) determine the abundance, distribution and survival of naturally produced fry and smolts in the Yakima River; (2) evaluate different methods of fry and smolt supplementation into the natural rearing environment while maintaining as much as possible the gentic integrity of naturally produced stocks; (3) locate and define areas in the watershed which may be used for the rearing of spring chinook; (4) define strategies for enhancing natural production of spring chinook in the Yakima River; and (5) determine physical and biological limitations for production within the system.

To make the coal-to-hydrogen route economically attractive, improvements are being sought in each step of the process: coal gasification, water-carbon monoxide shift reaction, and hydrogen separation. This report addresses the use of membranes in the hydrogen separation step. The separation of hydrogen from synthesis gas is a major cost element in the manufacture of hydrogen from coal. Separation by membranes is an attractive, new, and still largely unexplored approach to the problem. Membrane processes are inherently simple and efficient and often have lower capital and operating costs than conventional processes. In this report current ad future trends in hydrogen production and use are first summarized. Methods of producing hydrogen from coal are then discussed, with particular emphasis on the Texaco entrained flow gasifier and on current methods of separating hydrogen from this gas stream. The potential for membrane separations in the process is then examined. In particular, the use of membranes for H{sub 2}/CO{sub 2}, H{sub 2}/CO, and H{sub 2}/N{sub 2} separations is discussed. 43 refs., 14 figs., 6 tabs.

The United States Department of Energy is committed to the principles of minimizing the quantity and transuranic content of its transuranium (TRU) waste being generated at its nuclear facilities. The reasons are to reduce costs associated with waste handling and disposal, and also to reduce radiation exposure to workers and risk for radionuclide release to man and the environment. The purpose of this document is to provide the USDOE with a plan of research and development tasks for waste minimization, and is prepared so as to provide the maximum impact on volumes based on cost/benefit factors. The document is to be updated annually or as needed to reflect current and future tasks. The Reduced Waste Generation (RWG) tasks encompass a wide range of activities with the principal goals of (1) preventing the generation of waste and (2) converting TRU waste into low-level wastes (LLW) by sorting or decontamination. Concepts for reducing the volume such as in incineration and compaction are considered within the discipline of Reduced Waste Generation, but are considered as somewhat developed technology with only a need for implementation. 33 refs.

This paper describes an alternative library of elementary functions prepared for use with the standard Fortran compiler under 4.2 BSD UNIX on a VAX 11/780. The library, written in C and based on the book ''Software Manual for the Elementary Functions'' by Cody and Waite, offers improved accuracy over the standard system library, as well as additional capabilities. Listings and output from the ELEFUNT suite of test programs are included in the appendix.

Heat transfer in evacuated-tube solar collectors with heat-pipe absorbers is compared with that for similar collectors with flow-through absorbers. In systems that produce hot water or other heated fluids, the heat-pipe absorber suffers a heat transfer penalty compared with the flow-through absorber, but in many cases the penalty can be minimized by proper design at the heat-pipe condenser and system manifold. The heat transfer penalty decreases with decreasing collector heat loss coefficient, suggesting that evacuated tubes with optical concentration are more appropriate for use with heat pipes than evacuated or non-evacuated flat-plate collectors. When the solar collector is used to drive an absorption chiller, the heat-pipe absorber has better heat transfer characteristics than the flow-through absorbers.

This report documents the design considerations and test results of two heat extraction systems for the ANL Research Salt Gradient Solar Pond (RSGSP). Since operation began in November 1980, the RSGSP has been used to study a wide variety of solar pond phenomena, and the behavior of the RSGSP without heat extraction has been well characterized. Heat extraction equipment was installed in the spring of 1984, with heat extraction experiments conducted the following summer and fall and in the fall of 1985. The experiments simulated the use of the solar pond for grain drying. The effects of both heat extraction methods on the stability of the salt gradient are investigated.

The influence of gamma irradiation on the reaction of actinide-doped borosilicate glass (SRL 165) in a saturated tuff environment has been studied in a series of tests lasting up to 56 days. The following conclusions were reached. The reaction of, and subsequent actinide release from, the glass depends on the dynamic interaction between radiolysis effects, which cause the solution pH to become more acidic; glass reaction, which drives the pH more basic; and test component interactions that may extract glass components from solution. The use of large gamma irradiation dose rates to accelerate reactions that may occur in an actual repository radiation field may affect this dynamic balance by unduly influencing the mechanism of the glass-water reaction. Comparisons between the present results and data obtained by reacting similar glasses using MCC-1 and NNWSI rock cup procedures indicate that the irradiation conditions used in the present experiments do not dramatically influence the reaction rate of the glass.

The performance of programs executing on vector computers is significantly improved when the number of accesses to memory can be reduced. Unrolling Fortran DO loops, followed by substitutions and eliminations in the unrolled code, can reduce the number of loads and stores. The unrolling transformation and associated transformations of Fortran DO loops are characterized, and a set of software tools to carry out these transformations is described. The tools use the machinery available in Toolpack and have been integrated into that environment. The results of applying these tools to a collection of linear algebra subroutines are included.

Proper charging is essential to achieve maximum performance and life of lead-acid batteries. Excessive overcharging gives rise to increased battery temperature, gassing rates, electrolyte maintenance, and component corrosion, whereas repeated undercharging causes a gradual decrease in battery capacity, which often becomes irreversible. To develop an optimal charge procedure, the relation between battery available capacity, applied overcharge, and the depth-of-discharge (DOD) level prior to charging needed to be established.

This study supplements a larger study of a solid breeder blanket design featuring lithium ceramic pins. This aspect of the study looks at tritium transport, release, and inventory within this blanket design. Li/sub 2/O and ..gamma..-LiAlO/sub 2/ are the two primary candidates for ceramic solid breeders. ..gamma..-LiAlO/sub 2/ was chosen for this blanket design due to its higher structural stability. Analysis of tritium behavior in solid breeder blankets is of great importance due to its impact on several critical issues: the generation of an adequate amount of fusion fuel, the safety-related issue of keeping radioactive blanket inventories as low as possible, and the release, purge, and economical processing of the bred tritium without undue contamination of the coolant and other reactor structures.

Results are reported of the Environmental Quality Verification Program, which is an expanded continuation of the program of environmental monitoring previously carried out by the Environmental Measurements Group of the Hazards Control Department. Data are reported on air, soils, water, vegetation, foodstuffs, and annual radiation doses at perimeter of facility.

The use of solid breeders in blanket components of fusion reactors is necessitated by the need for tritium breeding, with avoidance of problems arising from liquid metal breeders; such as corrosion and MHD pressure drop. The material 9-C (low activation equivalent of HT-9) is used for the outside structure of the module, as well as for solid breeder pin cladding. The first wall is cooled with high velocity helium through coolant channels, while the pins are cooled by helium in a cross-flow configuration. The first zone is made up entirely of beryllium pins for neutron breeding, and then two solid breeder zones follow. In order to minimize maintenance time, a satisfactory configuration has to withstand transient phenomena associated with power-ramps and shutdowns while giving optimal thermomechanical performance in reasonable lifetime. These objectives can be reached by selecting suitable geometry and material specifications as well as prescribed temperature histories. Finding the minimal allowable ramp rate for startup is important from the economy of the operation, since overly conservative startup can amount to substantial percentage of the power cycle. In the stage of preliminary design the main concern is failure of the cladding due to high stresses or large total strains. The …

General properties of monochromators are discussed, and some useful formulas for optical design are given. The discussion is limited to the Rowland reflection grating. Topics covered include focussing properties of a toroidal grating, aberrations, dispersion, resolution, and phase space acceptance. (LEW)

A key to the successful design of a fusion blanket is the distribution of the amount of structural material in the first wall and the blanket enclosing structure. The first wall must support dynamic and static mechanical loads and at the same time sustain the thermal gradients and erosion resulting from the plasma heat and particle fluxes. Dynamic and static loads require high flexural rigidity, which is influenced by flow channels designed to cool the high heat flux incident on the first wall. Since the first wall temperature is roughly proportional to its thickness, thermal stresses require a thin first wall. On the other hand, a thick wall is necessary to withstand surface erosion due to particle fluxes. A fesible design must therefore represent an optimal solution satisfying such conflicting requirements.

Crystals of ((CH/sub 3/)/sub 3/SiC/sub 5/H/sub 4/)/sub 3/U are orthorhombic, Pbca, with a = 22.630(8), b = 29.177(10) and c = 8.428(3) A at 23/sup 0/C. For Z = 8 the calculated density is 1.551 g/cm/sup 3/. The structure was refined by full-matrix least-squares to a conventional R factor of 0.041 (2251 data, F/sup 2/ > 2 sigma(F/sup 2/)). The uranium atom is bonded to the three cyclopentadienyl rings in a pentahapto fashion and is in the plane of the ring centroids. The U to ring distances are 2.54, 2.47 and 2.51 A, and the average U-C distance is 2.78 +- 0.04 A. 7 refs., 1 fig., 3 tabs.

Information compiled in 1985 while assessing the environmental impact of radionuclides previously discharged with aqueous releases from the Rancho Seco Nuclear Power Generating Plant is presented. In October 1984, the quantities of gamma-emitting radionuclides in water discharged to Clay Creek from the plant were reduced below operationally defined detection limits for liquid effluents. However, radionuclides previously discharged persist in the downstream environment and are found in many aquatic dietary components. /sup 134/Cs and /sup 137/Cs are the primary gamma-emitting radionuclides detected in the edible flesh of different fish, crayfish, and frogs. Coefficients for exponential equations are generated, from a least square analysis, that relate the change in concentration of /sup 137/Cs in fish to distance downstream and time between March and October 1985. Concentrations of /sup 137/Cs in surface creek sediments also decreased in the downstream direction much in the same manner as concentrations decreased in fish. However, there was no significant difference in the radiocesium concentrations in surface sediements collected from comparable locations during both 1984 and 1985.

Cross sections have been measured from 100 eV to 1 MeV by the neutron-time-of-flight technique. The capture events were recorded by detecting the prompt gamma-ray cascade with two C/sub 6/D/sub 6/ scintillators, and were normalized to standard gold cross sections. The background was determined experimentally by utilizing the ''black resonance'' technique. A /sup 6/Li-glass scintillator was used to monitor the neutron flux. A Maxwellian-averaged capture cross section at kT = 30 keV of 74 +- 3 mb for /sup 86/Sr, and 102 +- 4 mb for /sup 87/Sr. (LEW)

The purpose of the task was to assess the effect of potential new technologies, nuclear and non-nuclear, on safeguards needs and non-proliferation policies, and to explore possible solutions to some of the problems envisaged. Eight subdivisions were considered: New Enrichment Technologies; Non-Aqueous Reprocessing Technologies; Fusion; Accelerator-Driven Reactor Systems; New Reactor Types; Heavy Water and Deuterium; Long-Term Storage of Spent Fuel; and Other Future Technologies (Non-Nuclear). For each of these subdivisions, a careful review of the current world-wide effort in the field provided a means of subjectively estimating the viability and qualitative probability of fruition of promising technologies. Technologies for which safeguards and non-proliferation requirements have been thoroughly considered by others were not restudied here (e.g., the Fast Breeder Reactor). The time scale considered was 5 to 40 years for possible initial demonstration although, in some cases, a somewhat optimistic viewpoint was embraced. Conventional nuclear-material safeguards are only part of the overall non-proliferation regime. Other aspects are international agreements, export controls on sensitive technologies, classification of information, intelligence gathering, and diplomatic initiatives. The focus here is on safeguards, export controls, and classification.

This report contains descriptions of projects specifically related to anadromous salmonids. They include projects in the following categories: (1) fish and wildlife projects in western Montana; (2) fish health and physiology; (3) habitat enhancement and passage improvement - Oregon I; (4) passage improvement and natural propagation - Washington; (5) habitat enhancement and passage improvements - Oregon II; (6) future hydroelectric assessments; (7) habitat enhancement and passage improvement - Idaho; (8) downstream migration: flows and monitoring; (9) downstream migration: reservoir impacts; and (10) habitat evaluation and monitoring. (ACR)

The annual Smolt Monitoring Program is the result of implementation of Section 304(d)(2) of the Northwest Power Planning Council Fish and Wildlife Program. Survival was monitored for specific marked groups of steelhead and spring chinook. Survival through the mid-Columbia from Winthrop Hatchery and the Methow River to below Priest Rapids Dam was estimated. Estimation of survival of marked groups of steelhead from Little Goose Dam to below Ice Harbor Dam was attempted. Serious problems were evident in the Snake River survival data. A release strategy which avoids holding of control groups was tested with satisfactory results.

The objective was to develop methods for improving anadromous fish passage in the Lemhi River in east central Idaho. Alternatives assessed include flow concentration, fish screen improvement, groundwater augmentation, groundwater irrigation, water withdrawal reduction, return flow improvement, sprinkler irrigation, storage, and trap and haul. (ACR)