A computer code, TVENT, for predicting tornado-induced depressurization in air cleaning systems is described. TVENT easily fits on many computers with input/output formats that are familiar to most analysts and HVAC designers. Applications of TVENT to several nuclear facilities in Idaho, New York, and New Mexico are described. Flow-resistance data of HEPA filters for use in TVENT are also described. At low flow resistance appears to be mainly caused by a diffusion mechanism, while at high flow the resistance seems to be caused by the mechanism of momentum exchange.

The requirements are established for a prototype portable test set to be used for static overpressure measurement of air leakage in insulated and refrigerated truck bodies. The test set described is to be constructed as an independent system with no dependence on the local atmospheric conditions in which it is used, other than having available a pressurized air supply normally found in maintenance garages and manufacturing plants. This specification also covers the requirements for calibration, operation and maintenance instructions to be furnished with the equipment.

A hybrid passive/active solar heating system, featuring a passive air thermosiphon loop, is described. Heated air is supplied to a rock storage bin, coupled with blower-driven air distribution to the house. The house, of 246 m/sup 2/ (2650 ft/sup 2/) heated area and located in Santa Fe, New Mexico, also includes a greenhouse located under the planar collector array. Architectural features and construction details of the house, the solar collector, storage, and distribution system are presented. Representative results of three months of monitoring by the Los Alamos Scientific Laboratory of collector, rock bin, and greenhouse temperatures, as well as outside ambient temperature and insolation, are reported and discussed. Data recorded hourly since the system was placed in operation in early February 1978, show temperatures in the rock bin in excess of 71/sup 0/C (160/sup 0/F) and in the collector absorber mesh in excess of 93/sup 0/C (200/sup 0/F). Delivery temperatures from the charged bin, without auxiliary boost, range from 38 to 54/sup 0/C (100 to 130/sup 0/F).

Airborne plutonium-239 and americium-241 concentrations and fluxes were measured at six heights from 1.9 to 122 m on the Hanford meteorological tower. The data show that plutonium-239 was transported on nonrespirable and small particles at all heights. Airborne americium-241 concentrations on small particles were maximum at the 91 m height.

The problem of Alfven-wave oscillations in an anisotropic sphere is studied, and two solutions are presented. One solution is exact, involving an expansion of the current inside the sphere in a series of orthonormal modes. The second is approximate, based on a perturbation expansion of the induced fields and currents in powers of the sphere radius. The approximate solution can be applied to a material having a completely general conductivity tensor, while the exact solution is restricted to situations of high symmetry. As an illustration of these solutions, the resonant power absorption by electron-hole droplets in Ge is calculated explicitly. Size-dependent resonances, for which the resonant field increases with the drop radius, have been observed experimentally. The present calculation shows that such resonances occur both in the magnetic- and electric-dipole absorption, with the magnetic-dipole absorption being most intense for the drop sizes and frequencies under consideration, particularly for small drops. From the approximate solution, it is found that certain of the resonances can have a very strong dependence on the orientation of the magnetic field with respect to the crystal axes, similar to cyclotron resonance of an electron in Ge. As a second application of these results, the transition from …

The aim of the study of the ion--foil interaction is to provide as complete as possible a description of the state of the outgoing beam produced when ions are transmitted through thin foils and to construct a physical model of the interaction process which can explain these results. Results for the 3p/sup 1/P and 4d levels of He I are presented. These results furnish much descriptive information concerning the nature of the interaction, but not a complete model of the interaction process. They do suggest an important role for surface effects and are strongly suggestive of an important role in these processes for electron capture. 10 references. (JFP)

The objective of the Alloy Development for Irradiation Performance Program is the development of structural materials for use in the first wall and blanket region of fusion reactors. The goal of the program is a material that will survive an exposure of 40 MWyr/m/sup 2/ at a temperature which will allow use of a liquid-H/sub 2/O heat transport system. Although the ultimate aim of the program is development of materials for commercial reactors by the end of this century, activities are organized to provide materials data for the relatively low performance interim machines that will precede commercial reactors.

Ignition (or near-ignition) by alpha heating is a key objective for the achievement of economic fusion reactors. While good confinement of high-energy alphas appears possible in larger reactors, near-term tokamak-type ignition experiments as well as some concepts for small reactors (e.g., the Field-Reversed Mirror or FRM) potentially face marginal situations. Consequently, there is a strong motivation to develop methods to evaluate alpha losses and heating profiles in some detail. Such studies for a TFTR-size tokamak and for a small FRM are described here.

High-energy fusion-product (FP) transport is a central issue in fusion reactor development. FP's that escape and bombard the first wall can be a serious mechanism for wall erosion and the introduction of impurities back into the plasma. Well-confined FP's heat the plasma as they slow down, but the resulting thermalization profile determines FP accumulation as an impurity. Here, we describe computational methods to model these effects and discuss the implications for reactor design.

This is the seventh progress report of an on-going three year research effort to contribute to the development of a new and/or improved technology that will result in wide spread use of an anaerobic fermentation in agriculture to generate a renewable clean energy source. Activities are now concentrating on full-scale and pilot-scale demonstration of simplified fermentors for manures. Activities for the seventh quarter year, extending from December 16, 1977 to March 15, 1978, have included the following: completion of construction of the full scale conventional control fermenter; completion of construction, testing and startup of the random mix fermenter; installation of feed and effluent lines, electrical wiring, boilers, gas lines and controls; successful testing of the ram pump; conclusion of the 35/sup 0/C studies with the pilot scale plug flow fermenter and the initiation of the low temperature (25/sup 0/C) studies; and preparation of a detailed outline to the design manual. As of March 15, 1978, the overall progress achieved with the major components of the project was estimated to be about 2.5 months behind the work plan schedule. As detailed in the last progress report, much of this delay has been due to the winter weather (i.e., cold temperatures, snow, …

Monte Carlo calculations were made to analyze the results of an integral experiment with a sample of SiO/sub 2/ to determine the adequacy of ENDF/B-IV neutron scattering and gamma-ray production cross-section data for silicon and oxygen. The experimental results analyzed included energy-dependent NE-213 detector neutron and gamma-ray count rates at a scattering angle of 90 deg and pulse-height spectra for scattered neutrons and gamma rays. The experiments were carried out with the ORELA 1- to 20-MeV pulsed neutron source. The pulse-height data were unfolded to generate secondary neutron and gamma-ray spectra at 90 deg as a function of incident neutron energy. Multigroup Monte Carlo calculations using the MORSE code and ENDF/B-IV cross sections were made to analyze all reported results. No outstanding discrepancies between calculated and measured responses were found on the neutron data below 12 MeV. Possible discrepancies in the inelastic scattering data above 12 MeV are indicated. This is consistent with a previous analysis of an oxygen experiment. A more detailed analysis will have to be performed before any definite conclusions can be drawn from these comparisons.

Monte Carlo calculations were made to analyze the results of an integral experiment with an aluminum sample to determine the adequacy of ENDF/B-IV neutron scattering and gamma-ray production cross-section data for aluminum. The experimental results analyzed included energy-dependent NE-213 detector neutron and gamma-ray count rates at a scattering angle of 125 deg and pulse-height spectra for scattered neutrons and gamma-rays. The experiments were carried out with the ORELA 1- to 20-MeV pulsed neutron source. The pulse-height data were unfolded to generate secondary neutron and gamma-ray spectra at 125 deg as a function of incident neutron energy. Multigroup Monte Carlo calculations using the MORSE code and ENDF/B-IV cross sections were made to analyze all reported results. Discrepancies between calculated and measured responses were found for secondary neutron scattering data above 10 MeV and for gamma-rays produced at energies between 4 and 7 MeV. A detailed analysis has not yet been performed to determine the reasons for these discrepancies.

The objective of this research study is the development of radically new fluid systems, specifically tailored to the needs and requirements of solar-absorption cooling for single-family-size residences. Progress is reported.

A solar-powered cooling system which promises high system C.O.P.'s and low collector costs is analyzed. It consists of a desiccant and an absorption cooling system operating in series to both dry and cool the air. A common solution of lithium chloride is used as the absorbant. The lithium chloride solution is regenerated by evaporating the excess water to the atmosphere in an ''open'' collector. This collector consists merely of a blackened flat surface. The weak solution of lithium chloride is introduced at the top of the collector and then flows by gravity over the entire collector surface where it is subsequently heated and dried. The daily performance of this combined system is compared by computer simulation to that of either an absorption or desiccant system alone using actual weather data for five typical U.S. cities. The performance improvement of the combined system ranged from 25% to 95%, the greatest improvement being for humid, windy conditions.

The Lagrangian similarity theory and statistical theory are used to determine the form of the concentration distribution for a plume in the atmospheric boundary layer. The power of z in the concentration distribution is shown to be a slowly varying function of anti z and z/sub 0/.

The Laramie Energy Research Center (LERC) conducted an underground coal gasification experiment in a 9-m thick subbituminous coal seam near Hanna, Wyoming. Sandia Laboratories designed and fielded an extensive instrumentation array which included approximately eight thermocouples within the seam in each of 15 diagnostic wells. The instrumentation provided thermal data related to the process during both reverse combustion linkage and forward gasification. Portions of these data suitable for analysis by inverse heat conduction techniques included (1) the responses from the approximately cylindrical reverse combustion linkage path and (2) the responses at thermocouples outside the gasified zone due to conduction from the final boundary. Because of the effects of property variations and water vaporization on the conduction response, an exact analytical solution could not be used. Instead, the approach was to adjust parameters of the constant property analytical solutions to fit numerical calculations that included property variations and water vaporization. Sensitivity studies performed to estimate the accuracy of solutions obtained indicated that parameters relating to size and distance should be identifiable within +- 0.25 m; however, accurate estimates of temperature could not be obtained. Results allowed the position of the reverse combustion linkage path to be mapped, and estimates of its …

Large-area, positron-sensitive detectors are used in annihilation coincidence systems for studies with positron-decay radiopharmaceuticals. Factors which limit the spatial resolution in such systems are analyzed. These factors include: (1) the intrinsic spatial resolution of the detector, (2) parallax errors, (3) range of positrons in tissue, and (4) angular deviation of the coincident photon pair from colinearity.

This document analyzes past and present Federal incentives to production of various energy sources in order to assist in the study and recommendation of Federal incentives for the development of solar energy. The document was divided into five parts: a survey of current thought about incentives for solar energy production; the theoretical approach to analyzing and characterizing incentives; a generic view of the energy incentive-creating landscape for 1976; analysis of the major energy sources (nuclear, hydro, coal, oil, and gas) along their trajectories from exploration to waste management, including their costs in 1976 dollars; and insights into potential incentives for solar policy.

In its shielding program for the Gas-Cooled Fast Reactor (GCFR) as conceived by General Atomic, Oak Ridge National Laboratory has developed an advanced shielding analysis system that incorporates the latest analysis techniques for converging to a shield design compatible with other design parameters such as cooling and structural requirements or material compatibility. Basically the system consists in applying the various techniques in a logical sequence to a given design, thereby generating a large body of data to serve as an information base for subsequent redesign. As an illustration, this system is applied to successive typical models for the GCFR, resulting in a reduction in the thickness of the radial shield and redesign of the lower shield region. In principle, the design-analysis-redesign iterations would continue until they converge upon an acceptable configuration.

The issue of hypothetical whole-core accidents continues to play a significant role in assessment of the potential risk to the public associated with LMFBR operation in the USA. The paper briefly characterizes the changing nature of this role, with emphasis on the current risk-oriented perspective. It then describes the models and codes used for accident analysis in the USA which have been developed under DOE sponsorship and summarizes some specific applications of the codes to the current generation of fast reactors. An assessment of future trends in this area concludes the paper.

Major physical performance parameters and economic factors of a generalized redox-flow storage battery system are analyzed. The system is divided into power-related and energy-related subsystems. The economic factors include plant capital (and other) costs, electrical energy lost by the storage-cycle inefficiency, and a penalty term for failures. Relationships are formulated for the overall system efficiency and system performance parameters (voltages, current density, state-of-charge of the storage liquid, and parasitic losses). Equations for sizing and costing of the battery and the storage tank subsystems are given. Directions for needed research are indicated.

A new fuel pin failure model (the Los Alamos Failure Model), based on a linear life fraction rule failure criterion, has been developed and is reported herein. Excellent agreement between calculated and observed failure time and location has been obtained for a number of TOP TREAT tests. Because of the nature of the failure criterion used, the code has also been used to investigate the extent of cladding damage incurred in terminated as well as unterminated TOP transients in the FTR.

Many detailed multigroup transport calculations require group-to-group Legendre transfer coefficients to represent scattering processes in various nuclides. These (fine-group) constants must first be generated from the basic data. An alternative technique for generating such data from the total scattering cross section of a particular nuclide on a pointwise energy basis, sigma(E'), and some information regarding the angular scattering distribution for each initial energy point is outlined. The evaluation of generalized multigroup transfer matrices for transport calculations requires a double integration extending over the primary and secondary energy groups, where, for a given initial energy, the integration over the secondary energy group may be replaced by an integral over the possible scattering angles. In the present work, analytic expressions for these angular integrals are derived which are free of truncation error. Differences between the present method (as implemented in ROLAIDS) and other methods (as implemented in MINX and NEWXLACS) are explored. Of particular interest is the fact that, for hydrogen, the angular integration is shown to simplify to the point that, for many weight functions, the integration over the primary energy group might also be performed analytically. This completely analytic treatment for hydrogen has recently been implemented in NEWXLACS. 1 figure.

A prescription is given for finding coherent states in generalized potentials. By coherent states is meant states which in time follow the motion that a classical particle would. This prescription is based upon finding those natural classical variables which vary as the sine and the cosine of the classical ..omega../sub c/t. As an example, the symmetric Rosen--Morse potential is discussed in detail.