Two solar collectors using a pebble bed design were constructed and tested using air as the heat exchange media. One collector had pebbles of metallurgical grade coke, and the other had a frothy volcanic material called scoria. The highly irregular surface of such vesicular material should increase the path distance for the air and the surface exposed cavities should give some honeycomb effect. Both should yield greater efficiency. Actual testing shows the efficiencies to be comparable with other air collectors. Thus the advantages of the pebble bed lie in the availability of the bed material, its thermal and radiation stability, and its shielding of underlying collector materials from ultraviolet radiation. Several pebble bed collectors using water as the heat exchange media were constructed. However, basic problems prevented effective testing, and it is concluded that pebble bed collectors using water are impractical.

The effect of introducing a neutron and gamma shield into the annulus between the reactor vessel and the shield tank is analyzed. This addition has been proposed in order to intercept neutron streaming up the annulus during nuclear operations. Its installation will require removal of approximately 20-/sup 1///sub 2/ inches of stainless steel foil insulation at the top of the annulus. The resulting conduction path is believed to result in increased water temperatures within the shield tank, possibly beyond the 150/sup 0/F limit, and/or cooling of the reactor vessel nozzles such that adverse thermal stresses would be generated. A two dimensional thermal analysis using the finite element code COUPLE/MOD2 was done for the shield tank system illustrated in the figure (1). The reactor was assumed to be at full power, 55 MW (th), with a loop flow rate of 2.15 x 10/sup 6/ lbm/hr (268.4 kg/s) at 2250 psi (15.51 MPa). Calculations indicate a steady state shield tank water temperature of 140/sup 0/F (60/sup 0/C). This is below the 150/sup 0/F (65.56/sup 0/C) limit. Also, no significant changes in thermal gradients within the nozzle or reactor vessel wall are generated. A spacer between the gamma shield and the shield tank …

The present study indicates that the estimation of the gamma-ray strength function is the approach least subject to error when unmeasured capture cross sections are to be computed. An estimate is given for the /sup 88/..gamma..(n,..gamma..) cross section.

The objective of the work reported here was to develop a model which could be used to assess the economic effects of energy-conservative technological innovations upon the pipeline industry. The model is a dynamic simulator which accepts inputs of two classes: the physical description (design parameters, fluid properties, and financial structures) of the system to be studied, and the postulated market (throughput and price) projection. The model consists of time-independent submodels: the fluidics model which simulates the physical behavior of the system, and the financial model which operates upon the output of the fluidics model to calculate the economics outputs. Any of a number of existing fluidics models can be used in addition to that developed as a part of this study. The financial model, known as the Systems, Science and Software (S/sup 3/) Financial Projection Model, contains user options whereby pipeline-peculiar characteristics can be removed and/or modified, so that the model can be applied to virtually any kind of business enterprise. The several dozen outputs are of two classes: the energetics and the economics. The energetics outputs of primary interest are the energy intensity, also called unit energy consumption, and the total energy consumed. The primary economics outputs are …

In response to additional needs developed during a review of the LOFT Technical Specifications, two more pressure reduction and decontamination sump volume vs. initial temperature data points were calculated in order to adequately quench steam generator relief blowdown. The two additional points chosen were for 10,000 gallons (based on ECC requirements) and for 120/sup 0/F (NPSH limit maximum temperature). The results are that for 10,000 gallons in the sump the maximum initial temperature is 110/sup 0/F and for 120/sup 0/F initial temperature, a volume of 14,000 gallons is required in the sump. Calculations are shown on page two of this report. The maximum final PR and DS temperature was set at 140/sup 0/F to preclude the vibrational effects discussed in LTR 115-9 and its referenced operational experience reports.

Purex Sludge Supernatant (PSS) contains significant amounts of /sup 137/Cs left after removal of strontium from fission product bearing Purex wastes. To remove cesium from PSS, an Ion Exchange Recovery system has been set up in Cells 17-21 at B Plant. The cesium that is recovered is stored within B Plant for eventual purification through the Cesium Purification process in Cell 38 and eventual encapsulation and storage in a powdered form at the Waste Encapsulation Storage Facility. Cesium depleted waste streams from the Ion Exchange processes are transferred to underground storage.

ORCODE.77 is a versatile data-handling computer routine written in MACRO (assembler) language for a PDP-15 computer with EAE (extended arithmetic capability) connected to a CAMAC interface. The Interrupt feature of the computer is utilized. Although the code is oriented for a specific experimental problem, there are many routines of general interest, including a CAMAC Scaler handler, an executive routine to interpret and act upon three-character teletype commands, concise routines to type out double-precision integers (both octal and decimal) and floating-point numbers and to read in integers and floating-point numbers, a routine to convert to and from PDP-15 FORTRAN-IV floating-point format, a routine to handle clock interrupts, and our own DECTAPE handling routine. Routines having specific applications which are applicable to other very similar applications include a display routine using CAMAC instructions, control of external mechanical equipment using CAMAC instructions, storage of data from an Analog-to-digital Converter, analysis of stored data into time-dependent pulse-height spectra, and a routine to read the contents of a Nuclear Data 5050 Analyzer and to prepare DECTAPE output of these data for subsequent analysis by a code written in PDP-15-compiled FORTRAN-IV.

The DT fusion neutron irradiation of eleven BNL-LASL superconductor wires, one BPNL wire-foil packet, and two ORNL magnesium oxide crystals is described. The sample position and neutron dose record are given. The maximum neutron fluence on any sample was 2.77 x 10/sup 15/ neutrons/cm/sup 2/.

The PBXN-5 and PBX-9604 shock Hugoniots, longitudinal and shear sound velocities, and response to long and short duration shocks have been determined. At a density of 1.66 Mg/m/sup 3/, PBXN-5 requires a minimum copper flyer kinetic energy of 382 kJ/m/sup 2/ for initiation at a flyer velocity of 0.8 km/s. At a density of 1.49 Mg/m/sup 3/, PBX-9604 requires a minimum flyer energy of 201 kJ/m/sup 2/ for initiation at the same velocity.

The results of experimental work and economic analyses carried out during the first 12 months of this contract (Phase I) have led to Battelle's concentration on development of the zinc reduction of silicon tetrachloride on seed particles in a fluidized bed. A second year program (Phase II) has been initiated which consists of the design of a 25 MT/year experimental facility and supporting experiment effort. During this quarter, the effort in the plant design portion of the program has been devoted to the (1) preparation of a detailed process schematic diagram; (2) determination of material flow and energy requirements; (3) conceptual design of major equipment items, including those unique to the facility; (4) contacts with industrial companies on equipment and processes for which experience is available; and (5) initiation of contacts with Battelle pilot plant design specialists, a distillation consultant, and engineering firms. The effort in the experimental support portion of the program has included a continuation of the following studies: (1) operating parameter optimization in the miniplant, (2) reactor design, and (3) condenser system design, including supplemental condensation experiments. In addition, a new zinc feed system has been devised and evaluated, and the construction of a system sufficiently large …

In the work on prediction of calorimeter equilibrium, a newly derived single-exponential prediction equation has been shown to yield results equal to those from previously reported work, but allows for more versatility in the instrumentation selection. A single-precision rather than a double-precision calculator is all that is required to predict reliable equilibrium values using this new equation. A double-exponential prediction equation has also been derived and tested using simulated data. Engineering refinements have been incorporated in the Automated Plutonium Assay System (APAS) to provide for improvements in the gamma-ray spectroscopy system and the container pickup device. In addition, evaluation tests on the assay instrumentation have been conducted. Calorimeter tests indicate that values within 1 percent of equilibrium can be obtained in 7 min. The Half-Life Evaluation Committee has completed measurements of the half-life of /sup 239/Pu. Preliminary results show that measurements by alpha and gamma counting, by mass spectrometry and by calorimetry agree sufficiently well that a recommended value with a relative standard deviation of +-0.1 percent will be reported. Papers describing these measurements are being prepared for journal publication. The committee concurs with the recent recommendation by Argonne National Laboratory representatives that the value 87.74 +- 0.04 yr be …

The program consists generally of development of advanced conversion systems, with strong emphasis on a systems approach to find solutions of the problems of scale formation, corrosion/erosion of materials, spent brine disposal and solids handling, and development of reliable, efficient energy conversion systems with strong emphasis on development of the total flow concept. The status of the various parts of this program is reviewed briefly. (MHR)

The Site Data Acquisition Subsystem (SDAS) Mod 1 is designed to collect sensor measurement data from a solar energy demonstration site. A brief description of the SDAS is given and the installation requirements and procedures, the operations description and the procedures for field maintenance of the subsystem are defined.

As petroleum-based fuels grow increasingly scarce and costly, nuclear energy may become an important alternative source of industrial energy. Initial applications would most likely include a mix of fossil-fired and nuclear sources of process energy. A means for determining the overall reliability of these mixed systems is a fundamental aspect of demonstrating their feasibility to potential industrial users. Reliability data from nuclear and fossil-fired plants are presented, and several methods of applying these data for calculating the reliability of reasonably complex industrial energy supply systems are given. Reliability estimates made under a number of simplifying assumptions indicate that multiple nuclear units or a combination of nuclear and fossil-fired plants could provide adequate reliability to meet industrial requirements for continuity of service.

Progress is reported from studies on the physical oceanography and biology of coastal waters and the continental shelf off the coast of South Carolina, Georgia, and northeast Florida known as the SE Atlantic Bight. The data will be used as a basis for the evaluation of the environmental effects in the event of operation of off-shore energy facilities. Data are presented from studies of: water currents along shores, the net motion of intrusions from the Gulf Stream, and water exchange in estuaries; the flux and distribution of radioisotopes and heavy metals transported by rivers, the atmosphere, or intrusions; nutrient fluxes and the chemical composition of seawater from various locations; the role of pelagic microorganisms in the cycling, production, and distribution of organic matter; and the biomass of phyto- and zooplankton associated with Gulf Stream intrusions.

Information obtained from exploratory drilling of potential coal-gasification sites in the Powder River Basin of Wyoming and Montana is summarized. The objectives were to obtain stratigraphic descriptions of the coal-bearing strata from cuttings and geophysical logs, determine the hydrologic characteristics of the coal and associated strata, and see if there were drilling and logging problems associated with deep, thick coal seams. It was decided to do preliminary hydrologic and gasification experiments on the shallower Felix coal before proceeding to more deeply buried coals. The types of information obtained included geophysical borehole logs, lithologic and stratigraphic logs derived from drill cutting samples, drilling rate data, stratigraphic columns showing the depth and thickness of the coal and associated strata, log analyses showing lithology, computer-generated average porosity, density and velocity, composition diagrams of the geophysical logs run and the lithologic correlations picked from the logs, and coal analysis from selected Felix Coal cores. Specific results are reported in numerous tables, graphs and survey charts.

Progress is reported in the following LMFBR piping design studies: development of a long range plan to secure piping integrity, collection of piping failure and construction defect data, analysis of systems with prior successful operating history, evaluation of sensitivity of piping design margins to variability in materials and geometry, and high cycle fatigue behavior at elevated temperature.

Heat transfer from the sides and bottom of an open non-boiling liquid pool with spatially uniform internal gas injection was studied experimentally, both in transient and in steady state. The results were compared with experimental data for a boiling pool without permanent gas injection undertaken at Argonne National Laboratory. Typical Nusselt number versus Reynolds number plots showed that heat transfer rates were much higher in the gassy pool due to more efficient circulation. A correction was applied to estimate the surface evaporation effect under boiling conditions. Bubble size and distribution effects controlled the heat transfer rates. Vertical void fraction profiles were inferred from local static pressure measurements. A modified Grashof number, in terms of the average void fraction, was also used to correlate the data for horizontal heat flow. The bottom and side heat loss rates were about equal, which would indicate that the pool might retain its shape as it sinks into the support material.

The program is designed to investigate how certain metallurgical characteristics control the hydrogen absorption and desorption processes in intermetallic compounds. The status of the following studies is reported: hydrogen safety precautions, development of special equipment, preparation and characterization of hydride alloy materials, magnetic property measurements, and theoretical modeling of hydriding mechanisms. (LK)