This report contains the results of that analysis, and a review of critical management issues for the Federal Aviation Administration (FAA) has been added to the basic questions about the adequacy of Federal standards and programs. During the course of the study, it became clear that a full report for Congress would have to consider how policy is determined and implemented, and thus the operation of FAA and the role of the Department of Transportation.

The topic of this fourth paper in OTA’S series of AIDS-related issues is the impact of the AIDS epidemic on the Kaiser Permanence Medical Care Program’s (KPMCP) northern California region and was originally commissioned for OTA’s assessment of Medical Testing and Health Insurance. Key OTA staff involved in the oversight of the project were Jill Eden, Larry Miike, and Laurie Mount.

This report focuses on the formal policies and guidelines’ through which health care institutions articulate decision making procedures and identify permissible options regarding the use of life-sustaining treatments for adult patients in their care.

Adequate, reliable space transportation is the key to this Nation’s future in space. Over the next several years, Congress must make critical decisions regarding the direction and funding of U.S. space transportation systems. These decisions include improving existing launch systems, designing and procuring new launch systems, and developing advanced technologies. America’s constrained budgetary environment and the lack of a national consensus about the future of the U.S. space program make Congress’s role in this process more difficult and important than ever.

This special report is the fourth in a series of OTA studies being carried out under an assessment of “New Developments in Biotechnology, ” requested by the House Committee on Energy and Commerce and the House Committee on Science, Space, and Technology. This fourth report in the series describes the levels and types of investment currently being made by the Federal, State, and private sectors. Ten major issues that affect investment were identified.

This report discusses the frequency and timing of recommended child visits, and the frequency and timing of recommended screening tests or procedures in well child care.

This report presents the results of a survey concerning state transmission line certification and sitting procedures, and state energy planning processes.

This plan deals with water resources in the region consisting of Uvalde, Medina, Bexar, Comal and Hays Counties. It presents a policy framework for water resources planning between 1990-2040 and lays out the next steps for implementation.

This plan put forth by the Joint Committee on Water Resources deals with water resources in the region consisting of Uvalde, Medina, Bexar, Comal and Hays Counties, presents a policy framework for water resources planning between 1990-2040, and lays out the next steps for implementation.

Tests are ongoing at Argonne National Laboratory to examine the reaction of glass with water under conditions that may exist in the proposed repository at Yucca Mountain, Nevada. Examination of glass reaction using the Unsaturated Test method as applied to simulated defense glass (SRL 165 black frit based) and simulated West Valley glass (ATM-10) is ongoing. The tests on SRL 165 glass have been ongoing for 104 weeks with nonstoichiometric release of Li, Na, B, and actinide elements being observed throughout the test period. The tests on ATM-10 glass have been in progress for 26 weeks and it is too early in the test cycle to assess the glass reaction. The influence of penetrating gamma radiation on the reaction of synthetic nuclear waste glasses in tuff groundwater was also investigated. Modified MCC-1 static leaching experiments were performed under radiation exposures of 1 {times} 10{sup 3} R/h and O R/h at 90{degree}C. The groundwater was acidified by nitrous and nitric acids radiolytically produced in the air. The high bicarbonate ion concentration of the groundwater prevented the pH from dropping below 6.4, however. The glass reaction, as measured by the release of glass species and the thickness of an alteration layer formed …

Under provisions of the Surplus Facilities Management Program (SFMP), the US Department of Energy, Chicago Operations Office, proposes to provide funding for Surveillance and Maintenance (S & M) and subsequent Decontamination and Decommissioning (D & D) of fifteen facilities and associated premises belonging to Battelle Columbus Division. The fifteen facilities are contaminated as a result of nuclear research and development activities conducted over a period of approximately 43 years for DOE and its predecessor agencies--the Energy Research and Development Administration (ERDA), the Atomic Energy Commission (AEC) and the Manhattan Engineer District (MED). The proposed action includes continuation of ongoing S & M as well as a D & D of the facilities. The S & M activities include a continued environmental monitoring program to maintain assurance that radioactive contamination has not escaped to the surrounding environment; regularly scheduled inspection and maintenance of health, safety, and radiation protection equipment and instrumentation; a program of health physics surveillance monitoring, personnel dosimetry, and equipment and instrumentation maintenance and calibration; and emergency planning, training, and drills. The so- called dismantlement D & D mode is the proposed alternative for D & D of these facilities. For the facilities in question this will generally involve …

This appendix is an assessment of the present conditions of the inactive uranium mill site near Mexican Hat, Utah. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan. Plan is to characterize the conditions at the mill and tailings site so that the Remedial Action Contractor may complete final designs of the remedial action.

Several of the monitoring wells installed at the Savannah River Plant in the past few years exhibit pH values of 8 or higher. These pHs are significantly higher than average values for the aquifers involved and are also higher than expected for natural waters. They are also inconsistent with observations in nearby wells. It is therefore suspected that the high pHs are not representative of true aquifer conditions. Two previous studies conducted at SRP (Price, 1984; Schreeder, 1986) conclude that high pH readings in M-Area monitoring wells and Z-Area piezometers are the result of contact between groundwater and grout. Price bases his conclusion on water chemistry. Schreeder`s evidence is the relationship between pH and amount of water withdrawn from the piezometers--an initially high pH drops as more water is removed. This conclusion is supported by laboratory measurements on water samples collected from cement-bentonite grout which show pH values of 13. This investigation was undertaken to evaluate contamination by grout and drilling fluid as a possible cause of elevated pH in monitoring wells at SRP and to develop techniques to rehabilitate the affected wells. FSB and HSB wells were used in this study.

This Remedial Action Plan (RAP) has been developed to serve a two- fold purpose. It presents the activities proposed by the Department of Energy (DOE) to accomplish long-term stabilization and control of the residual radioactive materials (RRM) from Monument Valley Arizona, and Mexican Hat, Utah, at the Mexican Hat disposal site. It also serves to document the concurrence of both the Navajo Nation and the Nuclear Regulatory Commission (NRC) in the remedial action. This agreement, upon execution by DOE and the Navajo Nation and concurrence by the NRC, becomes Appendix B of the Cooperative Agreement. This document has been structured to provide a comprehensive understanding of the remedial action proposed for the Monument Valley and Mexican Hat sites. It includes specific design and construction requirements for the remedial action. Pertinent information and data are included with reference given to the supporting documents. Appendices A,B, and C are provided as part of this document. Appendix A presents regulatory compliance issues, Appendix B provides details of the engineering design, and Appendix C presents the radiological support plan.

This document provides Appendix E of the Remedial Action Plan (RAP) presented in 1988 for the stabilization of the inactive uranium mill tailings at the Mexican Hat, Utah site. The RAP was developed to serve a two- fold purpose. It presents the activities proposed by the Department of Energy (DOE) to accomplish long-term stabilization and control of the residual radioactive materials (RRM) from Monument Valley, Arizona, and Mexican Hat, Utah, at the Mexican Hat disposal site. It also serves to document the concurrence of both the Navajo Nation and the Nuclear Regulatory Commission (NRC) in the remedial action. This agreement, upon execution by the DOE and the Navajo Nation and concurrence by the NRC, becomes Appendix B of the Cooperative Agreement. The RAP has been structured to provide a comprehensive understanding of the remedial action proposed for the Monument Valley and Mexican Hat sites. It includes specific design and construction requirements for the remedial action.

This note will wrap up the numerical results that were obtained in our calculations of the wake potentials, the loss factors, and the impedances for a variety of structures in the APS storage ring. It consists of five sections and one appendix. Section 1 is an introduction. Section 2 summarizes the hand calculations. The computer calculations are the subject 1 of Section 3. Section 4 discusses several tests in our numerical methods. Section 5 presents the APS impedance budget, along with some discussion. The appendix contains the figures of the structures, the longitudinal/transverse wake potentials and the real/imaginary part of the impedances of various sorts of geometries that have been included in the budget.

This report gives an approved set of material properties over a range of environmental conditions which are sufficient to design the metallic components in the reactor system and hot duct assembly. Table 1-1 list these metallic components together with the reference design material chosen for each component. Table 1-2 summarizes the structural criteria of each metallic component taken from the component specifications. In all cases, the criteria references the ASME B&PV Code. The ASME-Code includes the material properties of Coded material. The Code does not, however, include environmental effects (such as irradiation, corrosion, or thermal aging), and for some components the material maximum allowable temperature is below that of the design and/or postulated ``safety-related`` accident conditions. Table 1-3 gives the Code limits for the portions of the Code given in Table 1-2. This document includes the effects of the radiation environment, chemical impurity effects (in the primary coolant), and the effects of thermal aging and corrosion on the metallic properties. The design information introduced in this document includes that available from the ASME B&PV Code High-Temperature Code Cases plus material information from General Atomics (GA) and Oak Ridge National Laboratories (ORNL) that is published.

Report of activities at Argonne involving the Atmospheric Fluidized-Bed Cogeneration Air Heater Experiment.

During this report period, all experiments were conducted with tuff from the proposed high-level nuclear waste site at Yucca Mountain, Nevada. Batch sorption ratio determinations were conducted for strontium, cesium, uranium, and technetium onto samples of tuff using real and synthetic groundwater J-13. There were no significant differences in sorption ratios in experiments with real and synthetic groundwater. Columns were tested by determination of elution curves in J-13 containing tritium and technetium as the TcO{sub 4}/sup {minus}/ ion. For strontium and cesium, fairly good correlation between values of the sorption ratio obtained by the two methods was observed. Little technetium sorption was observed with either method. The elution peaks obtained with neptunium and uranium were asymmetrical and the shapes were often complex, observations which suggest irreversibilities in the sorption reaction. Synthetic groundwater J-13 was slowly dripped onto a slab of tuff maintained at 95--100{degree}C, and the result was a thin encrustation of solids on the slab as the water evaporated. Fresh J-13 groundwater was then allowed to contact the encrustation in a vessel maintained at 90{degree}C. The principal result of the experiment was a significant loss of calcium and magnesium from the fresh J-13 groundwater. 13 refs. 25 figs., 9 …

This report consists of vugraphs of a presentation on the thermoelectric-electromagnetic pump. Topics covered are: modeling methodology; summary of rectangular TEMP results; cylindrical TEMP optimization task; optimization approach; optimization results; discussion of cylindrical optimization; and thoughts on future work.

Available irradiation creep data on H-451 graphite area analyzed and fitted to the proposed creep model in a standard linear solid (a linear viscoelastic model). A creep equation is obtained and recommended for preliminary design use. It is found that the regression is significant and the creep equation is a good predictor. The standard error (SE) of the estimate is smaller than that used in the core graphite criteria development. This smaller SE shall be used in all future work related to criteria development. The creep coefficient and/or model can be further improved if additional creep data can be obtained. For this purpose several creep experiments are recommended. The immediate one is to capsule 87M-2A currently under design.

Compilation of monthly reports from departments in the city of San Antonio, Texas providing statistics, project updates, and other information about services and activities.

The impedances and the loss factors experienced by a particle beam that circulates in the APS storage ring play an essential role in the studies of the beam instability problem. Due to a large variety of structures in the ring, the computation of these parameters amounts to enormous work. During the last months, this was tackled numerically by invoking the MAFIA family, a set of codes developed mainly at DESY. The results are to be reported in several LS notes. This note is the first part and will discuss a composition rule that we observed in our calculations. The composition rule can be stated as follows. For a complicated structure, one may decompose it into simple components and compose these components to form new structures. Under certain conditions, the old and the new structures will give the same loss factors. This rule is in analogy to and an extension of the law of addition of resistances in sequence in the conventional circuit theory. We will discuss two examples to illustrate this rule.

Technological breakthroughs cannot be penciled on the calendar in advance. The rate of new technological discovery, while highly uncertain, depends on a base of knowledge acquired earlier. In the economic environment of 1980, progress in basic research, which builds the technology base that will underpin future energy development by Government and industry, was being slowed as cost increases due to inflation grew faster than funding increase.