Abstract: The circumstances leading to the second phase of the Air-Launched Balloon System Development Program are described, along with the governing design constraints. Individual component development efforts and system design modifications are described in turn: the procurement and testing of the new dewar, the qualification of the updated cryogenic unit recovery system. The complicated command, control, and telemetry subsystem is also described in detail. The results of component tests and a system dress rehearsal system tests are summarized. Preparations for two full-scale system tests conducted in 1981 are covered in considerable detail. The results of those tests are presented and the test data are analyzed. It is concluded that the system's air-launch and mid-air inflation techniques are acceptable. The balloon requires structural reinforcements, however, before the system can be said to be fully developed.

Several pinhole collimator geometries for use in neutron imaging experiments have been modeled and compared. Point spread functions are shown for a cylinder, hyperbola, intersecting cones, and a five-zone approximation to the intersecting cones. Of the geometries studied, the intersecting cones appear the most promising with respect to neutron efficiency, field of view, and isoplanatism.

This project, Energy Recovery Through Termites, was based on the proposed development of an energy recovery system to produce low cost animal protein for use in animal feeds. The result of my study shows that to date we are unable to establish viable colonies of termites. This is based on several key factors as follows: (a) inability to capture reproductives to establish new colonies in a confined area needed to offer recovery or harvest of protein; (b) confinement of colonies (even without queen or reproductives) has proven to be far too complex to establish in low cost and modest facilities; (c) the proposal is not cost effective. The resources of skill and materials could not be repaid from the protein recovered.

A financial accounting model that incorporates physical and institutional uncertainties has been developed for geothermal projects. Among the uncertainties it can handle are well depth, flow rate, fluid temperature, and permit and construction times. The outputs of the model are cumulative probability distributions of financial measures such as capital cost, levelized cost, and profit. These outputs are well suited for use in an investment decision incorporating risk. The model has the powerful feature that conditional probability distribution can be used to account for correlations among any of the input variables. The model has been applied to a geothermal reservoir at Heber, California, for a 45-MW binary electric plant. Under the assumptions made, the reservoir appears to be economically viable.

The objective of the Spent Fuel Stabilizer Materials Program is to identify, test, select, and qualify stabilizer materials for use in the design of spent fuel waste packages. Emphasis is placed on the selection of stabilizer materials with minimal interactions. The preliminary screening of candidate spent fuel stabilizer materials was completed and reported to the Office of Nuclear Waste Isolation in November 1980. Based on criteria set for thermally induced stresses, material cost, and material availability, an initial list of potential stabilizers was reduced to 34 that are recommended for additional screening tests. The spent fuel stabilizer temperature limit test was completed during this report period. Tests were conducted to establish a conservative temperature limit for spent light water reactor (LWR) fuel during the stabilizer emplacement process. Melting of metals and metal alloys, fusing of glass stabilizers,or other possible emplacement processes may require elevation of the spent fuel temperature above levels desirable for maintaining fuel rod integrity (intact cladding) or reasonable inter-rod spacing for stabilizer flow. This test was conducted to establish the temperature below which these concerns would not exist. Stabilizers that require emplacement process temperatures above the limit will be eliminated from the screening program.

This contract study of basic combustion and pollutant formation processes for pulverized solid fossil fuels includes coal-water mixtures and chars derived from coal pyrolysis, liquefaction or gasification processes. The factors that affect the physical properties of coal-water mixtures (CWM) have been identified and characterization tests initiated to determine how these variables (e.g., solids loading, particle size, particle size distribution, additives) affect the coal slurries. A bench-scale apparatus consisting of a pressure vessel and an atomizing nozzle was designed and is being fabricated. This apparatus will assist in the development of handling and atomization techniques for the combustion tests. It will also aid in comparing viscosities of slurries of different solids loadings and coal types. Chars were obtained for characterization tests. A series of potential tests to characterize the chars was identified. Grading and sizing of the chars was begun as well as elemental analysis. Samples of the chars were sent to Phillips for CO/sub 2/ reactivity tests to be performed. Coding for incorporation of swirling flows into the two-dimensional coal combustion model (PCGC-2) was completed. Debugging was initiated and sample computations are performed for a gaseous, isothermal system for low swirl numbers. Convergence problems were encountered when attempts were made …

Research on this contract can be divided into two general topics: (1) D/sup -/ formation collision processes, and (2) the determination of scattering cross sections used to diagnose properties of magnetically-confined plasmas. For topic (1) during last year, we completed theoretical calculations on the differential (angular) scattering of H/sup 0/ and D/sup 0/ on Cs, and determined the mechanisms and trends in the electron detachment cross sections for collisions of H/sup -/ and D/sup -/ on He, Ne, and the alkali and heavy alkaline earth atom systems. On topic (2) a major accomplishment was the determination of the electron capture and ionization cross sections for the C/sup 5 +/, N/sup 5 +/, and O/sup 6 +/ + H systems in the energy range from 13 eV/amu to 2.1 MeV/amu.

This report is a compilation of abstracts of papers, reports, and talks presented during 1980 at national and international meetings by members of the Earth Sciences Division, Lawrence Livermore National Laboratory. The arrangement is alphabetical (by author). For a given report, a bibliographic reference appears under the name of each coauthor, but the abstract itself is given only under the name of the first author (indicated in capital letters) or the first Earth Sciences Division author.

"Field and laboratory data are presented for 1937 sediment samples from the Ely Quadrangle, Nevada; Utah. The samples were collected by Savannah River Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee." (Abstract)

"Field and laboratory data are presented for 1038 sediment samples from the Fresno Quadrangle, California. The Samples were collected by Savannah River Laboratory; Laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee." (Abstract)

"Field and laboratory data are presented for 1890 sediment samples from the Sacramento Quadrangle, California. The samples were collected by Savannah River Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee." (from Abstract)

Field and laboratory data are presented for 1937 sediment samples from the Ely Quadrangle, Nevada; Utah. The samples were collected by Savannah River Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee.

Field and laboratory data are presented for 1038 sediment samples from the Fresno Quadrangle, California. The samples were collected by Savannah River Laboratory; laboratory analysis and data reporting were perfomed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee.

Field and laboratory data are presented for 1890 sediment samples from the Sacramento Quadrangle, California. The samples were collected by Savannah River Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee.

The SARP includes discussions of structural integrity, thermal resistance, radiation shielding and radiological safety, nuclear criticality safety, and quality control. Extensive tests and evaluations were performed to show that the container will function effectively with respect to all required standards and when subjected to normal transportation conditions and the sequence of four hypothetical accident conditions (free drop, puncture, thermal, and water immersion). In addition, a steady state temperature profile and radiation profile were measured using two heat sources that very closely resemble the GPHS. This gave an excellent representation of the GPHS temperature and radiation profile. A nuclear criticality safety analysis determined that all safety requirements are met.

A process for producing panels for solar heating of potable water is described. The panels have PVC tubing flat-coiled into square or rectangular shapes. Also described is a cistern for collecting and storing rainwater. (LEW)

Weekly report of the Texas Crop and Livestock Reporting Service on turkey poult numbers in Texas and compared with other states. It includes compiled statistics across six consecutive weeks during two years for turkey eggs set and poults hatched.

This document is an interim report under ACDA BOA AC9NX707, Task Order 80-03, which covers the evaluation of certain potential improvements in pressurized water reactor designs intended to enhance uranium fuel utilization. The objective of these evaluations is to seek advanced, non-retrofittable improvements that could possibly be commercialized by the end of the century, and, on the basis of a preliminary evaluation, to select compatible improvements for incorporation into a composite advanced pressurized water reactor concept. The principal areas of investigation include reduced parasitic absorption of neutrons (Task 1), reduced neutron leakage (Task 2), and alternative fuel design concepts (Task 3). To the extent possible, the advanced concept developed in an earlier study (Retrofittable Modifications to Pressurized Water Reactors for Improved Resource Utilization, SSA-128, October 1980) is used as a basis in developing the advanced composite concept. The reference design considered typical of present PWR commercial practice is the system described in RESAR-414, Reference Safety Analysis Report, Westinghouse Nuclear Energy Systems, October 1976.

This report evaluates the enhanced resource utilization in an advanced pressurized water reactor (PWR) concept using a composite of selected improvements identified in a companion study. The selected improvements were in the areas of reduced loss of neutrons to control poisons, reduced loss of neutrons in leakage from the core, and improved blanket/reflector concepts. These improvements were incorporated into a single composite advanced PWR. A preliminary assessment of resource requirements and costs and impact on safety are presented.

As part of its program to help improve electrical power plant productivity, the Department of Energy (DOE) has developed a methodology for evaluating productivity improvement projects. This handbook presents a simplified version of this methodology called the Availability Improvement Methodology (AIM), which provides a systematic approach for prioritizing plant improvement projects. Also included in this handbook is a description of data taking requirements necessary to support the AIM methodology, benefit/cost analysis, and root cause analysis for tracing persistent power plant problems. In applying the AIM methodology, utility engineers should be mindful that replacement power costs are frequently greater for forced outages than for planned outages. Equivalent availability includes both. A cost-effective ranking of alternative plant improvement projects must discern between those projects which will reduce forced outages and those which might reduce planned outages. As is the case with any analytical procedure, engineering judgement must be exercised with respect to results of purely mathematical calculations.

Objective is to assess the reliability of steam generators of pressurized water reactor (PWR) power plants in the United States and abroad. The assessment is based on operation experience of both domestic and foreign PWR plants. The approach taken is to collect and review papers and reports available from the literature as well as information obtained by contacting research institutes both here and abroad. This report presents the results of the assessment. It contains a general background of PWR plant operations, plant types, and materials used in PWR plants. A review of the worldwide distribution of PWR plants is also given. The report describes in detail the degradation problems discovered in PWR steam generators: their causes, their impacts on the performance of steam generators, and the actions to mitigate and avoid them. One chapter is devoted to operating experience of PWR steam generators in foreign countries. Another discusses the improvements in future steam generator design.

Two sets of parameters have been developed to study stochastic accumulation. The question arises of the size of the transverse emittance required to achieve an antiproton yield of 1.2 x 10{sup 8} {bar p}'s/MR cyc1e for 4.5 GeV and 8 GeV {bar p} kinetic energies, given a full momentum acceptance of 4%. The results quoted in the paper are obtained with a Monte Carlo program which uses a fit to the {bar p} production invariant cross section that has been presented previously. An article describing the program is in preparation.

Enthalpy measurements were initiated on the model compound quinoline. Preliminary results are presented for the temperature region 186 to 732/sup 0/F along isobars of 75, 100, and 200 psia.

The incinerators developed and/or used for radioactive waste combustion are discussed and suggestions are made for uses of incineration in radioactive waste management programs and for incinerators best suited for specific applications. Information on the amounts and types of radioactive wastes are included to indicate the scope of combustible wastes being generated and in existence. An analysis of recently developed radwaste incinerators is given to help those interested in choosing incinerators for specific applications. Operating information on US and foreign incinerators is also included to provide additional background information. Development needs are identified for extending incinerator applications and for establishing commercial acceptance.