This report consolidates various data on the national debt; it presents changes and comparisons of the debt for the years 1955 to 1980. The report also contains information on the public debt limit, the ownership of the public debt, and the debt owed by several sectors of the economy.

This paper sets forth questions that a congressional office needs to consider in the process of closing down. These include statutory and non-statutory matters such as staff, the franking privilege, retirement benefits for Members and staff, allowances, and the disposition of congressional papers, and other office items.

This report presents a general analysis of personal staff functions in a congressional office. Because there is little specific information from Congress and other sources regarding staff job descriptions and because congressional office organization patterns very significantly, this report focuses on the staff functions that are common to all offices regardless of organizational structure or job title: office management; mail; projects; casework; legislation; schedulng and personal services; press and public relations; and political functions.

The report examines the current debate in the United States over proposals for increased U.S. military sales to China. The study first examines the background of U.S.-China security ties since the Nixon Administration, and then sets forth the parameters of the current debate by noting a number of issues concerning U.S. military transfers to China on which all sides generally agree. It shows that Americans familiar with the issue tend to identify with different groups of opinion or "schools of thought" on the question of U.S. military transfers to China, and provides a detailed pro-con analysis of the issue. It concludes by noting cross pressures that are likely to greet U.S. policy makers as they grapple with this issue in the months ahead and offers an assessment of four policy options of possible use by U.S. policymakers.

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A case study commissioned by the Office of Technology Assessment (OTA) that attempts to "advance the state of the art cost-effectiveness analysis (CEA) as the technique pertains to disease prevention and health promotion programs," using cervical cancer screening as the object of analysis (Summary).

A case study by the Office of Technology Assessment (OTA) that "touches on only some of the aspects of technology assessment that might be undertaken with respect to multichannel chemistry analyzers" (p. 7).

A report by the Office of Technology Assessment (OTA) that "presents an analysis of the cost and efficacy of the current use of upper gastrointestinal endoscopy" (p. 3).

A report by the Office of Technology Assessment (OTA) that compares and assesses different methods of treating periodontal disease (p. 3).

A case study by the Office of Technology Assessment (OTA) that focuses on bone marrow transplantation "presents both a critical analysis of the technology itself and policy options that would strengthen control over the rate of technological diffusion" (p. 3).

From abstract: "Survey of the Soviet effort in underground coal gasification and summarizes research conducted at the Podmoskovnaya Station until its close in 1963."

The purpose of this Public Participation Plan is to explain the Department of Energy`s plan for involving the public in the decision-making process related to the Uranium Mill Tailings Remedial Action (UMTRA) Project. This project was authorized by Congress in the Uranium Mill Tailings Radiation Control Act of 1978. The Act provides for a cooperative effort with affected states and Indian tribes for the eventual cleanup of abandoned or inactive uranium mill tailings sites, which are located in nine western states and in Pennsylvania. Section 111 of the Act states, ``in carrying out the provisions of this title, including the designation of processing sites, establishing priorities for such sites, the selection of remedial actions and the execution of cooperative agreements, the Secretary (of Energy), the Administrator (of the Environmental Protection Agency), and the (Nuclear Regulatory) Commission shall encourage public participation and, where appropriate, the Secretary shall hold public hearings relative to such matters in the States where processing sites and disposal sites are located.`` The objective of this document is to show when, where, and how the public will be involved in this project.

Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to the Center for Human Radiobiology. This report discusses an inquiry into the mechanisms and dosimetry for induction of malignancies by radium, and studies of individuals exposed to radium and thorium, as well as to other radionuclides,.

Response-surface techniques have been developed for obtaining probability distributions of the consequences of postulated nuclear reactor accidents. In these techniques, probability distributions are assigned to the system and model parameters of the accident analysis. A limited number of parameter values (called knot points) are selected and input to a deterministic accident-analysis code. The results of the deterministic analyses are used to generate analytical functions (called response surfaces) that approximate the accident consequences in terms of selected system and model parameters. The response-surface methodology of this report includes both systematical and random knot-point selection schemes, second- and third-degree response surfaces, functional transformations of both input parameters and consequence variables, smooth synthesis of region-wise response surfaces and the treatment of random conditions for conditional distributions. The computer code PROSA-2 developed for implementing these techniques is independent of the deterministic accident-analysis codes.

A comparative economic analysis was made of four solidification processes for liquid high-level radioactive waste. Two processes produced borosilicate glass monoliths and two others produced metal matrix composites of lead and borosilicate glass beads and lead and super-calcine pellets. Within the uncertainties of the cost (1979 dollars) estimates, the cost of the four processes was about the same, with the major cost component being the cost of the primary building structure. Equipment costs and operating and maintenance costs formed only a small portion of the building structure costs for all processes.

This report is the third in a series of reports describing studies of sorption and migration of radionuclides in tuff. The investigations were extended to lithologies of tuff not previously studied. Continuing experiments with uranium, plutonium, and americium are described. The dependence of sorption on the concentration of the sorbing element and on the solution-to-solid ratio was investigated for a number of nuclides and two lithologies. A circulating system was designed for measuring sorption ratios. Values obtained from this system, batch measurements, and column elutions are compared. Progress on measuring and controlling Eh is described.

Mapping of geologic discontinuities has been done in several phases at the Spent Fuel Test-Climax (SFT-C) in the granitic Climax stock at the Nevada Test Site. Mapping was carried out in the tail drift, access drift, canister drift, heater drifts, instrumentation alcove, and receiving room. The fractures mapped as intersecting a horizontal datum in the canister and heater drifts are shown on one figure. Fracture sketch maps have been compiled as additional figures. Geologic mapping efforts were scheduled around and significantly impacted by the excavation and construction schedules. Several people were involved in the mapping, and over 2500 geologic discontinuities were mapped, including joints, shears, and faults. Some variance between individuals` mapping efforts was noticed, and the effects of various magnetic influences upon a compass were examined. The examination of compass errors improved the credibility of the data. The compass analysis work is explained in Appendix A. Analysis of the fracture data will be presented in a future report.

Initial runs were completed in a new solvent extraction facility that has been built for testing coprocessing flowsheets with simulated LWR and FBR fuel solutions. The equipment, which is assembled in glove boxes, includes three 16-stage miniature mixer-settler banks with associated in-line monitors, pumping equipment, and sampling apparatus. Following shakedown runs with solutions containing uranium only, two flowsheet test runs were made with a simulated LWR fuel solution (U/Pu = 100). The solution was fed to an extraction-scrub bank, where 30% tributyl phosphate in normal paraffin hydrocarbon diluent was used to coextract uranium and plutonium. The extract was fed to a second mixer-settler bank, where all of the plutonium was stripped into an aqueous product stream using hydroxylamine nitrate for plutonium reduction; a controlled fraction of the uranium was simultaneously stripped to produce a U/Pu ratio of {similar_to}2. The amount of the uranium stripped with the plutonium was regulated by careful control of an organic backscrub stream. Finally, the residual uranium in the solvent was stripped in the third mixer-settler bank. The success of the experiments depended on precise control of very low liquid flow rates, and on in-line monitors which indicated the uranium or total heavy-metal concentrations. The most …

Absolute fission rate measurements using modified National Bureau of Standards fission chambers were performed in the Fast Flux Test Facility at two core locations for isotopic deposits of {sup 232}Th, {sup 233}U, {sup 235}U, {sup 238}U, {sup 237}Np, {sup 239}Pu, {sup 240}Pu, and {sup 241}Pu. Monitor chamber results at a third location were analyzed to support other experiments involving passive dosimeter fission rate determinations.

Monthly reports documenting San Antonio municipal board activities and city permitting for April 1981.

This summary report presents information on the end-uses of energy in the residential sector of seven major OECD countries over the period 1960-1978. Much of the information contained herein has never been published before. We present data on energy consumption by energy type and end-use for three to five different years for each country. Each year table is complemented by a set of indicators, which are assembled for the entire 20-year period at the end of each country listing. Finally, a set of key indicators from each country is displayed together in a table, allowing comparison for three periods: early (1960-63), pre-embargo (1970-73), and recent (1975-78). Analysis of these results, smoothing and interpolation of the data, addition of further data, and analytical comparison of in-country and cross-country trends will follow in the next phase of our work.

This report discusses a number of aspects of cost/benefit (C/B) analysis for in-service inspection (lSI} of pressurized water reactor (PWR) steam generators (SGs) and identifies several problem areas that must be addressed prior to a full C/B analysis capability. Following a brief review of the impact of SG problems on the productivity of PWR units and of the scope and variability of SG problems among U.S. PWRs, various occupational implications of SG lSI are considered, namely manpower, time, and rad exposure. The opportunities provided by refueling outages in respect to lSI frequency and work time windows are reviewed. Indices for characterizing the nondestructive testing {NDT) information, rad exposure, $ impact, and manpower and time attributes of single ISIs and a series of ISIs over an arbitrary evaluation period are presented and calculated for a number of lSI cases using SG parameters for three typical PWR units. A comparison of the $ impact of unscheduled outages attributable to SG problems with the $ cost of ambitious lSI strategies indicates that the $ cost is virtually negligible for well-planned ISis. Considering the ALARA constraint on occupational rad exposure, the skilled manpower pool for NDT work appears to be the principal factor limiting …

Pacific Northwest Laboratory (PNL) conducted an comprehensive literature review of actual reactor decontamination processes that are currently available. In general, any decontamination process should be based on the following criteria: effectiveness, efficiency, safety, and waste production. The information that was collected and analyzed has been divided into three major categories of decontamination: chemical, mechanical, and electrochemical. Chemical methods can be further classified as either low-concentration, singlestep processes or high-concentration, single- or multistep processes. Numerous chemical decontamination methods are detailed. Mechanical decontamination methods are usually restricted to the removal of a contaminated surface layer, whlch limits their versatility; several mechanical decontamination methods are described. Electrochemical decontamination. is both fast and easily controlled, and numerous processes that have been used in industry for many years are discussed. Information obtained from this work is tabulated in Appendix A for easy access, and a bibliography and a glossary have been provided.

On November 29, 1979, the NRC sent a letter to 52 nuclear power plants requesting evacuation time estimates for 10 sectors within a 10-mile radius of each plant. The requirements for these evacuation times are contained in NUREG-0654, Rev. 1, and include such factors as population density, weather conditions, warning time, response time and confirmation time. Fifty responses were received. The analysis of these findings are presented for review.