This report (vol. 7) presents graphs of major neutron-induced interaction cross sections in the Experimental Cross Section Information Library (ECSIL) as of July 4, 1976. It consists primarily of interactions where a single data set contains enough points to show cross-section behavior. In contrast, vol. 8 of this UCRL-50400 series consists of interactions where more than one data set is needed to show cross section behavior. Thus, you can find the total, elastic, capture, and fission cross sections (along with the parameters anti ..nu.., ..cap alpha.., and eta) in vol. 7 and all other reactions in vol. 8. Data are plotted with associated cross section error bars (when given) and compared with the Evaluated Nuclear Data Library (ENDL) as of July 4, 1976. The plots are arranged in ascending order of atomic number (Z) and atomic weight (A). Part A contains the plots for Z = 1 to 55; Part B contains the plots for Z greater than 55.

This report (vol. 8) presents graphs of supplemental neutron-induced cross sections in the Experimental Cross Section Information Library (ECSIL) as of July 4, 1976. It consists of interactions where more than one data set is needed to show cross-section behavior. In contrast, vol. 7 of this UCRL-50400 series consists primarily of interactions where a single data set contains enough points to show cross-section behavior. Vol. 7 contains total, elastic, capture, and fission cross sections (along with the parameters anti ..nu.., ..cap alpha.., and eta). Volume 8 contains all other reactions. Data are plotted with associated cross-section error bars (when given) and compared with the Evaluated Nuclear Data Library (ENDL) as of July 4, 1976. The plots are arranged in ascending order of atomic number (Z) and atomic weight (A). Part A contains the plots for Z = 1 to 35; Part B contains the plots for Z greater than 35.

A Monte Carlo code was written that calculates the transport of neutrons, photons, and neutron-induced photons. The cross sections of these particles are derived from TARTNP's data base, the Evaluated Nuclear Data Library. The energy range of the neutron data in the Library is 10/sup -9/ MeV to 20 MeV; the photon energy range is 1 keV to 20 MeV. One of the chief advantages of the code is its flexibility: it allows up to 17 different kinds of output to be evaluated in the same problem.

Newsletter of the Texas Bureau of Disease Control and Epidemiology that lists the issues the newsletter has covered, and which volume (by week) they can be found in.

Indexes to the neutron-induced interaction data in the Experimental Cross Section Information Library (ECSIL) as of July 4, 1976 are tabulated. The tabulation has two arrangements: isotope (ZA) order and reaction-number order.

This report (vol. 7) presents graphs of major neutron-induced interaction cross sections in the Experimental Cross Section Information Library (ECSIL) as of July 4, 1976. It consists primarily of interactions where a single data set contains enough points to show cross section behavior. In contrast, vol. 8 of this UCRL-50400 series consists of interactions where more than one data set is needed to show cross section behavior. Thus, you can find the total, elastic, capture, and fission cross sections (along with the parameters ..nu.. bar, ..cap alpha.., and eta) in vol. 7 and all other reactions in vol. 8. Data are plotted with associated cross section error bars (when given) and compared with the Evaluated Nuclear Data Library (ENDL) as of July 4, 1976. The plots are arranged in ascending order of atomic number (Z) and atomic weight (A). Part A contains the plots for Z = 1 to 55; Part B contains the plots for Z is greater than 55.

This report (Vol. 8) presents graphs of supplemental neutron-induced cross sections in the Experimental Cross Section Information Library (ECSIL) as of July 4, 1976. It consists of interactions where more than one data set is needed to show cross-section behavior. In contrast, Vol. 7 of this UCRL-50400 series consists primarily of interactions where a single data set contains enough points to show cross-section behavior. In Vol. 7 can be found the total, elastic, capture, and fission cross sections (along with the parameters anti ..nu.., ..cap alpha.., and eta). Volume 8 contains all other reactions. Data are plotted with associated cross-section error bars (when given) and compared with the Evaluated Nuclear Data Library (ENDL) as of July 4, 1976. The plots are arranged in ascending order of atomic number (Z) and atomic weight (A). Part A contains the plots for Z = 1 to 35; Part B contains the plots for Z greater than 35.

The bibliographic citations in the Experimental Cross Section Information Library (ECSIL) as of July 4, 1976 are tabulated. The tabulation has three arrangements: alphabetically by author, alphabetically by publication, and numerically by reference number.

This review is intended as an up-to-date review of the scientific literature on TATB since its discovery as a high explosive. In particular, it focuses on clarifying our current understanding of the relationship between the structure of TATB and its unique thermal stability. We review a large number of different publications by many authors. A small portion of the work on TATB'' presented actually consists of experimental studies on TATB formulated as PBX-9502 or as LX-17. Where relevant, this distinction is indicated. However, inasmuch as this review focuses on thermal response and the relationship of chemical reactivity to the molecular and lattice structure of TATB as a pure material, results from these other formulations may not be directly applicable, and in general we have omitted them. 4 refs.

Program GROUPIE reads evaluated data in the ENDF/B format and uses these data to calculate Bondarenko self-shielded cross sections and multiband parameters. To give as much generality as possible, the program allows the user to specify arbitrary energy groups and an arbitrary energy groups and an arbitrary energy-dependent neutron spectrum (weighing function). To guarantee the accuracy of the results, all integrals are performed analytically; in no case is iteration or any approximate form of integration used. The output from this program includes both listings and multiband parameters suitable for use either in a normal multigroup transport calculation or in a multiband transport calculation. A listing of the source deck is available on request.

The computer code LINEAR converts evaluated cross sections in the ENDF/B format into a form that can be defined by applying linear--linear interpolation to energy and cross section parameters. The code also thins those sections already in that form. The main advantage of the code is that it eliminates the need for any subsequent code to consider anything but linear--linear data. 2 figures.

Experimental and evaluated integral parameters derived from nuclear plus interference differential elastic scattering cross sections are presented for all projectile/target combinations of the particles p, d, t, /sup 3/He, and ..cap alpha... The data include reaction rates, average fractional energy losses per collision and per unit path length, and average laboratory scattering cosines. The resulting parameters are of potential use in analysis of charged-particle transport.

The code SIGMA1 Doppler broadens evaluated cross sections in the ENDF/B format. The code can be applied only to data that vary as a linear function of energy and cross section between tabulated points. This report describes the methods used in the code and serves as a user's guide to the code. 6 figures, 2 tables.

Abstract: An ionization chamber for use in counting alpha particle activity from the air has been devised for counting samples collected with the electrostatic precipitator. The chamber is an adaptation of the breech-locking standard chamber, with a cylindrical high voltage electrode into which the collection foil is placed, and a coaxial rod as a collecting electrode. A geometrical efficiency of close to 50% is obtained.

A 1-MW geothermal wellhead power plant incorporating a Lysholm or helical screw expander (HSE) was field tested between 1980 and 1983 by Mexico, Italy, and New Zealand with technical assistance from the United States. The objectives were to provide data on the reliability and performance of the HSE and to assess the costs and benefits of its use. The range of conditions under which the HSE was tested included loads up to 933 kW, mass flowrates of 14,600 to 395, 000 lbs/hr, inlet pressures of 64 to 220 psia, inlet qualities of 0 to 100%, exhaust pressures of 3.1 to 40 psia, total dissolved solids up to 310,000 ppM, and noncondensible gases up to 38% of the vapor mass flow. Typical machine efficiencies of 40 to 50% were calculated. For most operations efficiency increased approximately logarithmically with shaft power, while inlet quality and rotor speed had only small effects. The HSE was designed with oversized internal clearances in the expectation that adherent scale would form during operation. Improvements in machine efficiency of 3.5 to 4 percentage points were observed over some test periods with some scale deposition. A comparison with a 1-MW back-pressure turbine showed that the HSE can compete …

We provide, on microfiche records, tabulated values for data points in the Experimental Cross-Section Information Library (ECSIL). The microfiche records also include corresponding bibliographic information and data indexes. ECSIL now contains 1,600,000 neutron-cross-section data points.

The ENDF/B-V Evaluated Neutron Data File has been tested for validity by comparing calculated and experimental values of k/sub eff/ for 66 critical assemblies and emission neutron spectra for 20 spheres that were pulsed with 14-MeV neutrons. 20 figures, 7 tables.

In an effort to assist the coal industry in complying with the applicable regulations, to design safe and environmentally acceptable disposal systems, and to encourage secondary use of coal mine waste, the US Department of Energy has initiated research programs to develop coal mine waste disposal and use technology. This study of the properties of mine wastes in the Midwestern coal fields has been limited to the waste materials obtained from underground coal mines and preparation plants attached to both underground and surface mines. The program has been divided into two phases. In Phase I, the 20 most important properties relevant to safe disposal, reclamation, underground disposal, and secondary uses have been identified. An inventory of the significant waste disposal sites in the Midwestern coal fields has been prepared. The site locations have been plotted on USGS maps. Estimates of coal production and coal mine waste production during the next 2 decades have been prepared and are presented in this report. Also, all available information obtained from a search of existing literature on physical and chemical properties, including analysis results of the general runoff from the refuse disposal areas, has been collected and is presented. In order to fill the …

Patent for an apparatus used to kill insectects, particularly boll weevils on cotton blooms. The apparatus is attached to a wagon which is driven through a cotton field, and the device knocks off the boll weevil eggs and then suctions them into the device and destroys them by fire.

Patent for well drill that enables its upper end to be struck without disengaging the cable with an objective to provide simple, inexpensive, and convenient use.

Patent for dislodging, collecting, and destroying bugs and weevils by shaking pests from cotton bushes and crushing them.

Patent for care of live stock and particularly the pod poles. This invention is to produce a pod designed to podding the animals when they are loading or unloading for the shipment.

Patent for a burner constructed to admit a force of steam or air is sent through the nozzle with assigning to the fuel in fuel reservoir. This invention is used to burn the heavy crude oil.

Patent for improved Parcel-Carrier Guard for bicycles. Specifically the patent helps to prevent contact with the parcel carrier guard and the front wheel.