This document provides estimates of the volume of sludge (1) expected from Integrated Process Strategy (IPS) processing of the fuel elements and (2) in the fuel storage canisters in K West Basin. The original estimates were based on visual observations of fuel element condition in the basin and laboratory measurements of KE canister sludge density. Revision 1 revised the volume estimates of sludge based on additional data from evaluations of material from the KW Basin fuel subsurface examinations and KW canister sludge characterization data. A nominal Working Estimate and an upper level Working Bound is developed for the canister sludge and the fuel wash sludge components in the KW Basin.

This document provides estimates of the volume of sludge expected from Integrated Process Strategy (IPS) processing of the fuel elements and in the fuel storage canisters in K East Basin. The original estimates were based on visual observations of fuel element condition in the basin and laboratory measurements of canister sludge density. Revision 1 revised the volume estimates of sludge from processing of the fuel elements based on additional data from evaluations of material from the KE Basin fuel subsurface examinations. A nominal Working Estimate and an upper level Working Bound is developed for the canister sludge and the fuel wash sludge components in the KE Basin.

This report reviews recent efforts to limit youth access to cigarettes through enforcement of federal and state laws prohibiting tobacco sales to minors. Under the federal Synar Amendment, states must conduct compliance checks and enforce their minimum age-of-sale laws or risk losing block grant funds

The Mixed Waste Focus Area (MWFA) Characterization Development Strategy delineates an approach to resolve technology deficiencies associated with the characterization of mixed wastes. The intent of this strategy is to ensure the availability of technologies to support the Department of Energy� s (DOE) mixed waste low-level or transuranic (TRU) contaminated waste characterization management needs. To this end the MWFA has defined and coordinated characterization development programs to ensure that data and test results necessary to evaluate the utility of non-destructive assay technologies are available to meet site contact handled waste management schedules. Requirements used as technology development project benchmarks are based in the National TRU Program Quality Assurance Program Plan. These requirements include the ability to determine total bias and total measurement uncertainty. These parameters must be completely evaluated for waste types to be processed through a given nondestructive waste assay system constituting the foundation of activities undertaken in technology development projects. Once development and testing activities have been completed, Innovative Technology Summary Reports are generated to provide results and conclusions to support EM-30, -40, or -60 end user/customer technology selection. The Active and Passive Computed Tomography non-destructive assay system is one of the technologies selected for development by the …

This paper summarizes the talks on alpha particle transport which were presented at the 5th International Atomic Energy Agency's Technical Committee Meeting on "Alpha Particles in Fusion Research" held at the Joint European Torus, England in September 1997.

Long-pulse fusion physics experiments can be performed economically via resistive electromagnets designed for thermally steady-state operation. Possible fusion experiments using resistive electromagnets include long-pulse ignition with deuterium-tritium fuel. Long-pulse resistive electromagnets are alternatives to today's delicate and costly superconductors. At any rate, superconducting technology is now evolving independent of fusion, so near-term superconducting experience may not ultimately be useful.

Separations requested SRTC study the autocatalytic decomposition of the hydroxylamine nitrate which may occur in the presence of concentrated nitric acid with respect to making-up cold feed solutions. The data obtained from this study will provide Separations an envelope within which safe operations can be conducted.

This Systems Engineering Implementation Plan (SEIP) describes the processes, products, and organizational responsibilities implemented by Project W-519 to further define how the project`s mission, defined initially by the Tank Waste Remediation System Phase 1 Privatization Infrastructure Project W-503 Mission Analysis Report (Hoertkorn 1997), will be accomplished using guidance provided by the Tank Waste Remediation System Systems Engineering Management Plan (SEMP) (Peck 1998). This document describes the implementation plans for moving from a stated mission to an executable cost, schedule, and technical baseline and to help ensure its successful completion of those baselines.

This document (Volume 1) is the preliminary design specification for the canisters to be used during the handling, storage, transportation, and repository disposal of Department of Energy (DOE) spent nuclear fuel (SNF). This document contains no procurement information, such as the number of canisters to be fabricated, explicit timeframes for deliverables, etc. A companion document (Volume 2) provides background information and design philosophy in order to help engineers better understand the established design requirements for these DOE SNF canisters.

Mercury emission compliance is one of the major potential challenges raised by the 1990 Clean Air Act Amendments. Simple ways of controlling emissions have not been identified. The variability in the field data suggests that inherent mercury emissions may be reduced if the source of this inherent capture can be identified and controlled. The key mechanisms appear to involve the oxidation of the mercury to Hg{sup 2}, generally producing the more reactive HgCl{sub 2}, followed by its capture by certain components of the fly ash or char. This research focuses on identifying the rate-limiting steps associated with the oxidation step. Work in this reporting period focused on the development of oxidation data as a function of temperature and HCl concentration. The temperature range was 800-1200 C. The results show a lower level of oxidation than indicated by the earlier data of Hall et al. (1991). One possible reason for this discrepancy was the preheating of the HCl stream in the Hall experiment, leading to the partial decomposition of the HCl into reactive species. In the present experiments, the HCl was injected as a cold stream. The measured oxidation at these conditions was substantially above that predicted by equilibrium, indicating the …

This report describes The Climate and Hydrologic History of Southern Nevada During Late Quaternary.

Abandoning superconductors for magnetic fusion reactors and instead using resistive magnet designs based on cheap copper or aluminum conductor material operating at "room temperature" (300 K) can reduce the capital cost per unit fusion power and simplify plant operations. By increasing unit size well beyond that of present magnetic fusion energy conceptual designs using superconducting electromagnets, the recirculating power fraction needed to operate resistive electromagnets can be made as close to zero as needed for economy without requiring superconductors. Other advantages of larger fusion plant size, such as very long inductively driven pulses, may also help reduce the cost per unit fusion power.

The Tokamak Fusion Test Reactor (TFTR) tritium retention experience is reviewed and the data related to models of plasma surface interactions. Over 3.5 years of TFTR deuterium-tritium operations, approximately 51% of the tritium injected into TFTR was retained in the torus. Most of this was subsequently recovered by glow discharges and air ventilation. Co-deposition rates for representative conditions in tritium operation were modeled with the BBQ code. The calculations indicate that known erosion mechanisms and subsequent co-deposition are sufficient to account for the order of magnitude of retention.

This document (Volume 2) is a companion document to a preliminary design specification for the design of canisters to be used during the handling, storage, transportation, and repository disposal of Department of Energy (DOE) spent nuclear fuel (SNF). This document contains no procurement information, such as the number of canisters to be fabricated, explicit timeframes for deliverables, etc. However, this rationale document does provide background information and design philosophy in order to help engineers better understand the established design criteria (contained in Volume 1 respectively) necessary to correctly design and fabricate these DOE SNF canisters.

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