This document provides the basis for future use of the 284-E Powerhouse Trench as a transport conduit for effluents discharged from the 284-E Powerhouse in accordance with the requirements of the State Waste Discharge Permit, ST 4502.

This document provides guidance for the production of safety analysis reports that must meet both DOE Order 5480.23 and STD 3009, and be in compliance with the DOE regulatory policy that imposes certain NRC requirements.

The Accelerator Production of Tritium (APT) Facility will generate radioactive waste during routine operations of the plant. All of the waste generated will be Low Level Radioactive Waste (LLRW) or Mixed Low Level Waste (MLLW). Some APT wastes to be generated contain combinations of short lived and long lived radionuclides exceeding the current Waste Acceptance Criteria (WAC) of all Department of Energy (DOE) disposal locations. Some of the wastes would be classified Greater Than Class C (GTCC) LLRW under the Nuclear Regulatory Commission. The Nuclear Regulatory Commission (NRC) specifies a geologic repository for GTCC wastes. The Department of Energy specifies in 5820.2A geologic disposal shall comply with both Nuclear Regulatory Commission regulations and EPA standards.

The Area 2 Photo Skid Wastewater Pit, Corrective Action Site (CAS) Number 02-42-03, the only CAS in Corrective Action Unit (CAU) Number 332, has been identified as a source of unquantified, uncontrolled, and unpermitted wastewater discharge. The Photo Skid was used for photographic processing of film for projects related to weapons testing, using Kodak RA4 and GPX film processing facilities for black and white and color photographs. The CAU is located in Area 2 of the Nevada Test Site, Nye County, Nevada. The CAS consists of one unlined pit which received discharged photographic process wastewater from 1984 to 1991. The Corrective Action Decision Document (CADD) and the Closure Report (CR) have been developed to meet the requirements of the Federal Facility Agreement and Consent Order (FFACO, 1996). The CADD and the CR for this CAS have been combined because sample data collected during the site investigation do not exceed regulatory limits established during the Data Quality Objectives (DQO) process. The purpose of the CADD and the CR is to justify why no corrective action is necessary at the CAU based on process knowledge and the results of the corrective action investigation and to request closure of the CAU. This document …

One of the most persistent political issues facing Congress in recent years is whether to require that the budget of the United States be in balance. Although a balanced federal budget has long been held as a political ideal, the accumulation of large deficits in recent years has heightened concern that some action to require a balance between revenues and expenditures may be necessary. The debate over a balanced budget measure actually consists of several interrelated debates, which this report addresses.

The authors study a general class of bicriteria network design problems. A generic problem in this class is as follows: Given an undirected graph and two minimization objectives (under different cost functions), with a budget specified on the first, find a subgraph from a given subgraph class that minimizes the second objective subject to the budget on the first. They consider three different criteria -- the total edge cost, the diameter and the maximum degree of the network. Here, they present the first polynomial-time approximation algorithms for a large class of bicriteria network design problems for the above mentioned criteria. The following general types of results are presented. First, they develop a framework for bicriteria problems and their approximations. Second, when the two criteria are the same they present a black box parametric search technique. This black box takes in as input an (approximation) algorithm for the criterion situation and generates an approximation algorithm for the bicriteria case with only a constant factor loss in the performance guarantee. Third, when the two criteria are the diameter and the total edge costs they use a cluster based approach to devise approximation algorithms. The solutions violate both the criteria by a logarithmic …

This report consists of a brief introduction to the federal budget process.

This report provides a brief introduction to the federal budget process. Key budget concepts and terminology are defined and explained. The separate procedures that make up the federal budget process are identified and their salient features described. While a complete understanding of federal budgeting probably can be obtained only after much observation and study of the process in operation, broad exposure to its rudiments is a useful first step. Various resources “for additional reading” are identified at the end of this report, which the reader may find helpful in exploring the subject in greater depth.

This calculation note supports the subsurface leak accident scenario which remains subsurface. It is assumed that a single walled pipe carrying waste from tank 106-C ruptures, releasing the liquid waste into the soil. In this scenario, the waste does not form a surface pool, but remains subsurface. However, above the pipe is a berm, 0.762 m (2.5 ft) high and 2.44 m (8 ft) wide, and the liquid released from the leak rises into the berm. The slurry line, which transports a source term of higher activity than the sluice line, leaks into the soil at a rate of 5% of the maximum flow rate of 28.4 L/s (450 gpm) for twelve hours. The dose recipient was placed a perpendicular distance of 100 m from the pipe. Two source terms were considered, mitigated and unmitigated release as described in section 3.4.1 of UANF-SD-WM-BIO-001, Addendum 1. The unmitigated consisted of two parts of AWF liquid and one part AWF solid. The mitigated release consisted of two parts SST liquid, eighteen parts AWF liquid, nine parts SST solid, and one part AWF solid. The isotopic breakdown of the release in these cases is presented. Two geometries were considered in preliminary investigations, disk …

This Interim Operational Safety Requirements document supports the authorization basis for interim operations and identifies restrictions on interim operations for the disposal and storage of solid waste in the Central Waste Complex. The Central Waste Complex Interim Operational Safety Requirements provide the necessary controls on operations in the Central Waste Complex to ensure the radiological and hazardous material exposure will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, 1327 the public and the environment.

Environmental and economical concerns over diminishing landfill space and the growing abundance of mixed plastic waste mandate development of viable strategies for recovering high-valued resources from waste polymers. Co-processing of waste polymer mixtures with coal allows for the simultaneous conversion of coal and plastics into high-valued fuels. However, there is limited information about the underlying reaction pathways, kinetics, and mechanisms controlling coal liquefaction in the presence of polymeric materials. A series of model compound experiments has been conducted, providing a starting point for unraveling the complex, underlying chemistry. Neat pyrolysis studies of model compounds of polyethylene and coal were conducted in batch reactors. Tetradecane (C{sub 14} H{sub 30} ) was used as a polyethylene mimic, and 4-(naphthylmethyl)bibenzyl (NBBM) was used as a coal model compound. Reaction temperatures were 420 and 500 C, and batch reaction times ranged from 5--150 minutes. Detailed product analysis using gas chromatography and mass spectrometry enabled the reactant conversion and product selectivities to be determined. Reaction of single components and binary mixtures allowed the kinetic coupling between feedstocks to be examined.

The CASIM Monte Carlo Program has been used for shielding calculations at RHIC. In the most common application, the "star density" is calculated at some (usually transverse) depth in some medium assumed to have a few percent water by weight (soil or concrete). In cases where the location of the source is not known, the maximum star density in the beam direction is used to evaluate the adequacy of the transverse shielding.

The original intention for this work was to impart the technology that was developed in the field of computational aeronautics to the field of computational physical oceanography. This technology transfer involved grid generation techniques and solution procedures to solve the governing equations over the grids thus generated. Specifically, boundary fitting non-orthogonal grids would be generated over a sphere taking into account the topography of the ocean floor and the topography of the continents. The solution methodology to be employed involved the application of an upwind, finite volume discretization procedure that uses higher order numerical fluxes at the cell faces to discretize the governing equations and an implicit Newton relaxation technique to solve the discretized equations. This report summarizes the efforts put forth during the past three years to achieve these goals and indicates the future direction of this work as it is still an ongoing effort.

This document provides a Computer Software management plan for a new Honeywell Modular Automation System (MAS) being installed in the Plutonium Finishing Plant (PFP). This type of system will be used to control new thermal stabilization furnaces, a vertical denitrator calciner, and a pyrolysis furnace.

This report identifies functions and requirements for the tritium process confinement and clean-up system (PCCS) and provides supporting technical information for the selection and design of tritium confinement, clean-up (stripping) and recovery technologies for new tritium processing facilities in the Accelerator for the Production of Tritium (APT). The results of a survey of tritium confinement and clean-up systems for large-scale tritium handling facilities and recommendations for the APT are also presented.

A nuclear criticality safety analysis has been performed for the storage of residual plutonium cementation containers, produced at the Plutonium Finishing Plant, in 55 gallon drums. This CSER increases the limit of total plutonium stored in each 55 gallon drum from 100 to 200 grams.

Under the grant, the applicant has developed a method of identifying poloidal and toroidal modes active in tokamak plasmas. Except complicated situations the method has shown to work well. Even with the limited applications, the advantage from the method is significant and even crucial. The method can be used to identify: (1) responsible coherent modes such as MHD or Resistive modes activity in plasma; (2) onset of instabilities; and can be used for (3) plasma controls. The method has been applied to the DIII-D tokamak experimental data, and some results are presented in this report. The authors also present how the method can be used for plasma controls.

The US is beginning work on an advanced, light-water reactor (LWR), spent nuclear fuel (SNF), waste package (WP) that uses depleted uranium dioxide (UO{sub 2}) fill. The Canadian nuclear fuel waste management program has completed a 15-year development program of its repository concept for CANadian Deuterium Uranium (CANDU) reactor SNF. As one option, Canada has developed a WP that uses a glass-bead or silica-sand fill. The Canadian development work on fill materials inside WPs can provide a guide for the development of LWR SNF WPs using depleted uranium (DU) fill materials. This report summarizes the Canadian work, identifies similarities and differences between the Canadian design and the design being investigated in the US to use DU fill, and identifies what information is applicable to the development of a DU fill for LWR SNF WPs. In both concepts, empty WPs are loaded with SNF, the void space between the fuel pins and the outer void space between SNF assemblies and the inner WP wall would be filled with small particles, the WPs are then sealed, and the WPs are placed into the repository.

The Transportable Vitrification System (TVS) is a transportable melter system designed to demonstrate the treatment of low-level and mixed hazardous and radioactive wastes such as wastewater treatment sludges, contaminated soils and incinerator ash. The TVS is a large-scale, fully integrated vitrification system consisting of melter feed preparation, melter, offgas, service, and control modules. The TVS was tested with surrogate waste at the Clemson University Environmental Systems Engineering Department`s (ESED) DOE/Industry Center for Vitrification Research prior to being shipped to the DOE Oak Ridge Reservation (ORR) K-25 site for treatment of mixed waste. This testing, along with additional testing at ORR, proved that the TVS would be able to successfully treat mixed waste. These surrogate tests consistently produced glass that met the EPA Toxicity Characteristic Leaching Procedure (TCLP). Performance of the system resulted in acceptable emissions of regulated metals from the offgas system. The TVS is scheduled to begin mixed waste operations at ORR in June 1997.

This report details work performed between Lockheed Martin Energy Systems, Inc. (LMES) and UTE Straight-O-Matic (UTE) under the National Machine Tool Partnership program. This work included the design and construction of an automatic straightness measuring system capable of retrofitting to existing machines. 1 fig.

This report provides background on the range of actions that might be termed foreign policy sanctions and the events that might necessitate their use. Criteria are offered that legislators might consider to judge when sanctions might be appropriate, approaches that might be effective, aspects of the use of sanctions that are sometimes overlooked or not considered fully. The report provides an uncomplicated "map" of where sanctions policies and options currently lay in U. S. law.

Research performed under this contract originated with the premise that much could be done to improve existing techniques for modeling the effects of convection on solidification in mixtures by eliminating arbitrary characterizations of the mushy region and its coupling with the melt. It was therefore proposed that a set of continuum conservation equations be derived from the principles of classical mixture theory and that the model concurrently treat melt, mushy and solid regions as a single domain (a continuum). The conservation equations would accommodate all pertinent convection effects, and closure would be achieved by assuming local composition equilibrium at phase interfaces. The need for simplifying assumptions concerning the geometric regularity of the interfaces would be eliminated, along with the need for separately tracking the interfaces and using moving numerical grids and/or coordinate mapping procedures. Accordingly, specific objectives of the work have been to (i) develop models and procedures for simultaneously solving the coupled set of conservation equations which govern mass, momentum, energy and species transfer for solidification in a mixture, (ii) use the models to predict, as a function of time and over a representative range of operating conditions, velocity, temperature, and composition fields throughout solid, mushy and liquid regions …

There were two major components in the Jet Propulsion Laboratory (JPL) Summer Teacher Enhancement Project (STEP). First, the Summer Institute was structured as a four-week, 4-credit-unit University course for middle school science teachers, and consisted of workshops, lectures, labs, and tours as activities. The second component consists of follow-up activities related to the summer institute's contents, and again is structured as a University credit-bearing course for participants to reinforce their summer training. Considerable information from the comments and course ratings as given by the participants is included.

A one-day meeting was held by the authors to evaluate how the strategic lab workshops would tie to this year`s tactical planning exercise. In particular, they wanted to find recent events that would support the tactical goal decisions of the Lab, and they wanted to find events that verify the Lab`s present course. The events which are each briefly discussed are: Galvin Commission recommends consolidating DOE defense labs (1995); Congressional subcommittee staff force budget cuts and consolidation (1995); 28% of DOE/DP budget held back pending completion of a clear 5-yr plan for nukes (1995); DOD and DOE focus on dual use (1995); LANL work includes weapons rebuilds (1995); LANL chosen by DOE to develop and test advanced remediation techniques (1995); AGEX/DARHT Project is stopped by suits from environmental activities (1996); Non-proliferation treaty renewed (1996); US complies with Comprehensive Test Ban Treaty (1996); Capability based deterrence policy put into place (1998); Stockpile shrinks to approximately 2000 weapons (2005); DOE weapons labs re-chartered as true national labs (1996); DOE terminates all nuclear weapons testing support (1996); Industrial projects at LANL up 20% from previous year (1997); NIST-ATP Program becomes an interagency process (1997); DOE warns that spent commercial reactor fuels is a …