Many studies have been performed in animals which mimic potential exposures of people in order to understand how factors modify radiation dose-response relationships. Cooperative analyses by investigators in different laboratories have a large potential for strengthening the conclusions that can be drawn from individual studies. When information on each animal is combined, then formal tests can be made to demonstrate that apparent consistencies or inconsistencies are statistically significant. Statistical methods must be carefully chosen so that differences between laboratories or studies can be controlled or described as part of the analysis in the interpretation of the conclusions. In this report, the example of bone cancer of the large number of studies of modifying factors for bone cancer available from studies in US and European laboratories.

When the Advisory Committee began work in April 1994 we were charged with determining whether the radiation experiments design and administration adequately met the ethical and scientific standards, including standards of informed consent, that prevailed at the time of the experiments and that exist today and also to determine the ethical and scientific standards and criteria by which it shall evaluate human radiation experiments. Although this charge seems straightforward, it is in fact difficult to determine what the appropriate standards should be for evaluating the conduct and policies of thirty or fifty years ago. First, we needed to determine the extent to which the standards of that time are similar to the standards of today. To the extent that there were differences we needed to determine the relative roles of each in making moral evaluations. In Chapter 1 we report what we have been able to reconstruct about government rules and policies in the 1940s and 1950s regarding human experiments. We focus primarily on the Atomic Energy Commission and the Department of Defense. In Chapter 2 we turn from a consideration of government standards to an exploration of the norms and practices of physicians and medical scientists who conducted research …

The US Geological Survey and the Idaho Department of Water Resources, in response to a request from the US Department of Energy, samples 18 sites as part of a long-term project to monitor water quality of the Snake River Plain aquifer from the southern boundary of the Idaho National Engineering Laboratory to the Hagerman area. Water samples were collected and analyzed for selected radionuclides, stable isotopes, inorganic constituents, and organic compounds. The samples were collected from seven irrigation wells, seven domestic wells, two springs, one stock well, and one observation well. Two quality assurance samples also were collected and analyzed. None of the radionuclide, inorganic constituent, or organic compound concentrations exceeded the established maximum contaminant levels for drinking water. Many of the radionuclide and inorganic constituent concentrations exceeded their respective reporting levels. All samples analyzed for dissolved organic carbon had concentrations that exceeded their minimum reporting levels.

The objective of Task 1 is to prepare and evaluate catalysts and to develop efficient reactor systems for the selective conversion of hydrogen-lean synthesis gas to alcohol fuel extenders and octane enhancers. Task 1 is subdivided into three separate subtasks: laboratory setup; catalysis research; and reaction engineering and modeling. Research at West Virginia University (WVU) is focused on molybdenum-based catalysts for higher alcohol synthesis (HAS). Parallel research carried out at Union Carbide Chemicals and Plastics (UCC&P) is focused on transition-metal-oxide catalysts. Accomplishments to date are discussed in this report. In Task 2, during the past three months, much has been accomplished in fuel testing. Several tests have been run on pure indolene, and the data have been analyzed from these tests. The two limiting alcohol blends have been made, sent out for analysis and the results obtained. The emissions sampling system is undergoing changes necessary for running alcohol fuels. A cylinder pressure measurement system has been installed.

The Savannah River Archaeological Research Program (SRARP) continued through FY95 with the United States Department of Energy to fulfill a threefold mission of cultural resource management, research, and public education at the Savannah River Site. Over 2,300 acres of land on the SRS came under cultural resources review in FY95. This activity entailed 30 field surveys, resulting in the recording of 86 new sites. Twenty-two existing sites within survey tract boundaries were revisited to update site file records. Research conducted by SRARP was reported in 11 papers and monographs published during FY95. SRARP staff also presented research results in 18 papers at professional meetings. Field research included several testing programs, excavations, and remote sensing at area sites, as well as data collection abroad. Seven grants were acquired by SRARP staff to support off-site research. In the area of heritage education, the SRARP expanded its activities in FY95 with a full schedule of classroom education, public outreach, and on-site tours. Volunteer excavations at the Tinker Creek site were continued with the Augusta Archaeological Society and other avocational groups, and other off-site excavations provided a variety of opportunities for field experience. Some 80 presentations, displays and tours were provided for schools, historical …

The term ``transition costs`` describes the potential revenue shortfall (or welfare loss) a utility (or other actor) may experience through government-initiated deregulation of electricity generation. The potential for transition costs arises whenever a regulated industry is subject to competitive market forces as a result of explicit government action. Federal and state proposals to deregulate electricity generation sparked a national debate on transition costs in the electric-utility industry. Industry-wide transition cost estimates range from about $20 billion to $500 billion. Such disparate estimates raise important questions on estimation methods for decision makers. This report examines different approaches to estimating transition costs. The study has three objectives. First, we discuss the concept of transition cost. Second, we identify the major cost categories included in transition cost estimates and summarize the current debate on which specific costs are appropriately included in these estimates. Finally, we identify general and specific estimation approaches and assess their strengths and weaknesses. We relied primarily on the evidentiary records established at the Federal Energy Regulatory Commission and the California Public Utilities Commission to identify major cost categories and specific estimation approaches. We also contacted regulatory commission staffs in ten states to ascertain estimation activities in each of these …

The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) refers to a set of several microcomputer programs that were developed to create and analyze probabilistic risk assessments (PRAs), primarily for nuclear power plants. The Graphical Evaluation Module (GEM) is a special application tool designed for evaluation of operational occurrences using the Accident Sequence Precursor (ASP) program methods. GEM provides the capability for an analyst to quickly and easily perform conditional core damage probability (CCDP) calculations. The analyst can then use the CCDP calculations to determine if the occurrence of an initiating event or a condition adversely impacts safety. It uses models and data developed in the SAPHIRE specially for the ASP program. GEM requires more data than that normally provided in SAPHIRE and will not perform properly with other models or data bases. This is the first release of GEM and the developers of GEM welcome user comments and feedback that will generate ideas for improvements to future versions. GEM is designated as version 5.0 to track GEM codes along with the other SAPHIRE codes as the GEM relies on the same, shared database structure.

This Progress Report summarizes the research endeavors of the Biology Division of the Oak Ridge National Laboratory during the period October 1, 1993, through September 30, 1995. The report is structured to provide descriptions of current activities and accomplishments in each of the Division`s major organizational units. Lists of information to convey the entire scope of the Division`s activities are compiled at the end of the report. Attention is focused on the following research activities: molecular, cellular, and cancer biology; mammalian genetics and development; genome mapping program; and educational activities.

A long-term assessment of the Waste Isolation Pilot Plant (WIPP) repository performance must consider the impact of gas generation resulting from the corrosion and microbial degradation of the emplaced waste. A multiphase fluid flow code, TOUGH2/EOS8, was adapted to model the processes of gas generation, disposal room creep closure, and multiphase (brine and gas) fluid flow, as well as the coupling between the three processes. System response to gas generation was simulated with a single, isolated disposal room surrounded by homogeneous halite containing two anhydrite interbeds, one above and one below the room. The interbeds were assumed to have flow connections to the room through high-permeability, excavation-induced fractures. System behavior was evaluated by tracking four performance measures: (1) peak room pressure; (2) maximum brine volume in the room; (3) total mass of gas expelled from the room; and (4) the maximum gas migration distance in an interbed. Baseline simulations used current best estimates of system parameters, selected through an evaluation of available data, to predict system response to gas generation under best-estimate conditions. Sensitivity simulations quantified the effects of parameter uncertainty by evaluating the change in the performance measures in response to parameter variations. In the sensitivity simulations, a single …

This document provides an overview of the process used to assess the performance of the Waste Isolation Pilot Plant (WIPP), a proposed repository for transuranic wastes that is located in southeastern New Mexico. The quantitative metrics used in the performance-assessment (PA) process are those put forward in the Environmental Protection Agency`s Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive flasks (40 CFR 191). Much has been written about the individual building blocks that comprise the foundation of PA theory and practice, and that WIPP literature is well cited herein. However, the present approach is to provide an accurate, well documented overview of the process, from the perspective of the mechanical steps used to perform the actual PA calculations. Specifically, the preliminary stochastic simulations that comprise the WIPP PAs of 1990, 1991. and 1992 are summarized.

This document is the August 1995 listing of publicly available documents that are issued by the Nuclear Regulatory Commission. The compilation is broken down into docketed and undocketed items, and each of these categories is further broken down into narrower categories. In general, the docketed items pertain to specific NRC licensees, while the undocketed items are of general interest to all licensees of a particular group.