The purpose of this calculation is to determine the surface dose rates of a codisposal waste package (WP) containing an intact seed assembly of the Shippingport light-water breeder reactor (LWBR) spent nuclear fuel (SNF) and the Savannah River Site (SRS) high-level waste (HLW) in glass form. The Shippingport LWBR SNF is loaded in a Department of Energy (DOE) standardized 18-in. canister. The canister is surrounded by five 4.5-m-long Hanford pour canisters containing the HLW glass. Gamma dose rate calculation for the WP containing only the HLW glass is also performed. The results will provide information about the contribution of DOE SNF to the total dose rate on the WP surfaces.

The degradation of fracture toughness, tensile, and Charpy-impact properties of Type 308 stainless steel (SS) pipe welds due to thermal aging has been characterized at room temperature and 290 C. Thermal aging of SS welds results in moderate decreases in Charpy-impact strength and fracture toughness. For the various welds in this study, upper-shelf energy decreased by 50-80 J/cm{sup 2}. The decrease in fracture toughness J-R curve or JIC is relatively small. Thermal aging had little or no effect on the tensile strength of the welds. Fracture properties of SS welds are controlled by the distribution and morphology of second-phase particles. Failure occurs by the formation and growth of microvoids near hard inclusions; such processes are relatively insensitive to thermal aging. The ferrite phase has little or no effect on the fracture properties of the welds. Differences in fracture resistance of the welds arise from differences in the density and size of inclusions. Mechanical-property data from the present study are consistent with results from other investigations. The existing data have been used to establish minimum expected fracture properties for SS welds.

This report presents a revision of the procedure and correlations presented earlier in NUREG/CR-4513, ANL-90/42 (June 1991) for predicting the change in mechanical properties of cast stainless steel components due to thermal aging during service in light water reactors at 280-330 C (535-625 F). The correlations presented in this report are based on an expanded data base and have been optimized with mechanical-property data on cast stainless steels aged up to {approx}58,000 h at 290-350 C (554-633 F). The correlations for estimating the change in tensile stress, including the Ramberg/Osgood parameters for strain hardening, are also described. The fracture toughness J-R curve, tensile stress, and Charpy-impact energy of aged cast stainless steels are estimated from known material information. Mechanical properties of a specific cast stainless steel are estimated from the extent and kinetics of thermal embrittlement. Embrittlement of cast stainless steels is characterized in terms of room-temperature Charpy-impact energy. The extent or degree of thermal embrittlement at 'saturation,' i.e., the minimum impact energy that can be achieved for a material after long-term aging, is determined from the chemical composition of the steel. Charpy-impact energy as a function of time and temperature of reactor service is estimated from the kinetics of …

Without a large number of new trims the best way to fix the closed orbits in the debuncher is to move quads. There are some obvious features in the vertical orbit, Figure 1, that look like they are indeed orbit distortions. The horizontal orbit, Figure 2, also has some systematic features that can be removed by moving a small number of quads. It is likely that removing these orbit distortions will help in improving the aperture. In addition, the second order effects of such large offsets in the closed orbit, like changes in phase advance due to the sextapoles, could improve operations.

The purpose of deceleration studies is to construct the deceleration ramp files that are used to decelerate antiproton beam for experiment E835. A deceleration ramp file is a set of ramp tables that are downloaded to PAUX (a part of the Pbar front end) prior to a deceleration. There is a ramp table for each device that is changed during a deceleration. These tables determine how PAUX changes each device setting during a deceleration. Appendix 1 gives a table of all ramped devices. Presently a deceleration to the lowest energy allowed by our ramps requires the use of three ramp files: the first decelerates the beam from 8801 MeV/c to 6367 MeV/c, the second from 6367 MeV/c to 4858 MeV/c, and the third from 4858 MeV/c to 3900 MeV/c. At the time of this writing the third ramp file has yet to be completed. An important new feature of the present deceleration ramp files is that the value of {gamma}{sub t} is decreased as the beam is decelerated so that the Accumulator is always above transition.

This report describes the development of a Spatial Database Manager (SDBM) shell/interface which will provide information to users on how to collect, store, analyze, interpret, visualize and present data in an integrated reservoir characterization study. SDBM will provide access to various geologic, reservoir visual data via a well log interpretation program (Crocker Petrolog), mapping and cross section software ( the GeoGraphix Exploration System Workbench) and a volume visualization application. Data tables for geochemical and petrographic data, well logs, well header information, well production data, formation tops, and fault trace data have been completed. Spectral mineral data are currently being collected which will ultimately be used for identification of mineral assemblages. The geochemical program CHILLER is being used to model fluid-rock interactions and possibly porosity predictions.

Tank 241-BY-103 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. The drivers and objectives of waste tank headspace sampling and analysis are discussed in {open_quotes}Program Plan for the Resolution of Tank Vapor Issues.{close_quotes} Tank 241-BY-103 was vapor sampled in accordance with {open_quotes}Data Quality Objectives for Generic In-Tank Health and Safety Issue Resolution.{close_quotes}

The continuity equation for electromagnetic (EM) energy flow is used to describe radiation flow in the transport regime. The scheme of a discrete representation of H_z and a stochastic representation of H_x, H_y gives an effectively continuous representation of directed energy in the x-y plane, such that the ray effect of transport theory is absent. Since the in-plane amplitudes are generated at each time step, it is necessary to store only the perpendicular amplitudes and the results appear to be robust with respect to the coarse of this discretization.

This administrative report is of historical interest. It covers research on Hydrothermal, Geopressured Geothermal, Hot Dry Rock systems, and the Long Valley Experimental (occasioned originally by the Magma Energy Program). (DJE 2005)

This report is intended to provide a general understanding of the social costs associated with electric power generation. Based on a thorough review of recent literature on the subject, the report describes how these social costs can be most fully and accurately evaluated, and discusses important considerations in applying this information within the competitive bidding process. [DJE 2005]

Enhancer of gene silencing 1 (egs1) is an Arabidopsis mutant that enhances post-transcriptional gene silencing of the rolB gene introduced by genetic engineering (transgene). The goal of our proposal was cloning EGS1 based on its map position. Although we screened more than 2000 chromosomes for recombination, we were unable to get closer than 2 cM to the gene. We experienced an unexpected tendency of the post-transcriptionally silenced transgene to switch to a more stable silenced state. This made it impossible to select egs1 homozygotes for map based cloning. This forced us to reconsider our cloning strategy. One possibility would have been to use a different transgene as the target of gene silencing. We tested two other transgenes. Both encoded proteins unrelated to the first but they were all expressed from the same type of promoter and they all had a similar tendency to become post-transcriptionally silenced. After screening over 80 F2 segregants from each cross between our egs1 mutant and Arabidopsis of the same ecotype homozygous for the new transgene, we were disappointed to find that the egs1 mutation did not enhance post-transcription silencing of the two new genes. In 80 plants we expected to have between 4 and 6 …

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By attending the conference, participants learn about new and planned OEM vehicle and engine technologies; studies comparing Diesel and gasoline emissions to natural gas; new state and federal legislation; and innovative marketing programs they can use to help sell their products and services.

This Interface Control Document (ICD) describes the interface between the Double-Shell Tank (DST) System and T Plant. T Plant generates waste during decontamination activities. These facilities do not have a direct physical interface since the waste will be moved by tank trailer to the 204-AR waste unloading facility. The purpose of the ICD process is to formalize working agreements between the River Protection Project (WP) DST System and organization/companies internal and external to RPP. This ICD has been developed as part of the requirements basis for design of the DST System to support the Phase I Privatization effort.

This document contains impacts, plans, resource requirements, schedules, and documents to ensure the conduct of activities for the operation of the Hanford Action Tracking System (HATS). Each discrete topic in this document applies to a specific area of management and team interaction. These formally establish the planning, resources, documentation, and training responsibilities for the system management team. This document is composed of four appendices. These include the following: (1) organization impacts and implementation plan--expected organizational impacts resulting from setting up the new support system for the HATS, the plan to address each of these impacts and other system implementation requirements; (2) training and information requirements--training and information needed to use and operate the HATS; (3) operation/maintenance resources--resources required to maintain and operate the HATS once the system becomes operations; (4) training package--HATS implementation training needs, includes a training procedure, the environment for training users (tools and materials required for the facility, trainer, and trainee); schedule, and handout materials and forms to be completed at the time of training.

The Uranium Industry Annual 1994 (UIA 1994) provides current statistical data on the US uranium industry`s activities relating to uranium raw materials and uranium marketing during that survey year. The UIA 1994 is prepared for use by the Congress, Federal and State agencies, the uranium and nuclear electric utility industries, and the public. It contains data for the 10-year period 1985 through 1994 as collected on the Form EIA-858, ``Uranium Industry Annual Survey.`` Data collected on the ``Uranium Industry Annual Survey`` (UIAS) provide a comprehensive statistical characterization of the industry`s activities for the survey year and also include some information about industry`s plans and commitments for the near-term future. Where aggregate data are presented in the UIA 1994, care has been taken to protect the confidentiality of company-specific information while still conveying accurate and complete statistical data. A feature article, ``Comparison of Uranium Mill Tailings Reclamation in the United States and Canada,`` is included in the UIA 1994. Data on uranium raw materials activities including exploration activities and expenditures, EIA-estimated resources and reserves, mine production of uranium, production of uranium concentrate, and industry employment are presented in Chapter 1. Data on uranium marketing activities, including purchases of uranium and enrichment …

A limited study consisting of scoping experiments was carried out to determine if a uranium-niobium alloy was weakly or strongly resistant to penetration by liquid aluminum alloy 6061. Our investigation was limited to temperatures between 700{degrees}and 900{degrees}C and carried out using small cylindrical coupons of U-6wt.%Nb and unalloyed U in unsaturated molten aluminum and aluminum alloy 6061 baths. The results indicate that indeed, significant dissolution of uranium into molten aluminum occurs and in relatively short times. The diameters of U-6wt.%Nb test cylinders immersed in unsaturated Al-6061 decreased linearly with time at 700{degrees}C, 800{degrees}C, and 900{degrees}C at rates of 1.14 mm/h, 3.0 mm/h, and 3.5 mm/h, respectively. However, we have found that the reaction rates were significantly reduced by the alloying elements niobium and magnesium. These results suggest that a more detailed investigation could lead to a predictive capability for control of these reaction rates. In unalloyed U, the rate of U dissolution increased by up to a factor of ten relative to that in U- 6wt.%Nb. In both materials, the dissolution of the U core was found to occur by advance of a continuous intermetallic layer, which redissolves into the unsaturated liquid Al bath. The Nb additions resulted in the …

This Corrective Action Investigation Plan (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV); the State of Nevada Division of Environmental Protection (NDEP); and the US Department of Defense (FFACO, 1996). The CAIP is a document that provides or references all of the specific information for investigation activities associated with Corrective Action Units (CAUs) or Corrective Action Sites (CASs). According to the FFACO, CASs are sites potentially requiring corrective action(s) and may include solid waste management units or individual disposal or release sites (FFACO, 1996). Corrective Action Units consist of one or more CASs grouped together based on geography, technical similarity, or agency responsibility for the purpose of determining corrective actions. This CAIP contains the environmental sample collection objectives and the criteria for conducting site investigation activities at CAU 135, Area 25 Underground Storage Tanks (USTs), which is located on the Nevada Test Site (NTS). The NTS is approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada.

Operational Final Test Report for Integrated Systems, Project W-030 (Phase 2 test, RECIRC and HIGH-HEAT Modes). Project W-030 provides a ventilation upgrade for the four Aging Waste Facility tanks, including upgraded vapor space cooling and filtered venting of tanks AY101, Ay102, AZ101, AZ102.

The Richland Operations Office (RL) and Office of River Protection (ORP) are pleased to issue the attached Pollution Prevention Progress Report. We have just met the most aggressive waste reduction and A recycling goals to date and are publishing this report to recognize A the site's progress, and to ensure it will sustain success beyond 1 Fiscal Year 2000. This report was designed to inform the been made by RL and ORP in Waste Minimization (WMin) and Pollution Prevention (P2). RL, ORP and their contractors are committed to protecting the environment, and we reiterate pollution prevention should continue to be at the forefront of the environmental cleanup and research efforts. As you read the attached report, we believe you will see a clear demonstration of RL and ORP's outstanding performance as it has been responsible and accountable to the nation, its employees, and the community in which we live and work. commitment that all employees have for environmental stewardship. The report provides useful information about the U.S. Department of Energy's (DOE'S) environmental policy and programs, and contains countless examples of waste minimization projects. This year was the first year our site received the White House Closing the Circle in the …

The following description and any attachments and references are provided to the Washington State Department of Health (WDOH), Division of Radiation Protection, Air Emissions & Defense Waste Section as a notice of construction (NOC) in accordance with Washington Administrative Code (WAC) 246-247, Radiation Protection - Air Emissions. WAC 246-247-060, ''Applications, registration, and licensing'', states ''This section describes the information requirements for approval to construct, modify, and operate an emission unit. Any NOC requires the submittal of information listed in Appendix A,'' Appendix A (WAC 246-247-110) lists the requirements that must be addressed. Additionally, the following description, attachments, and references are provided to the U.S. Environmental Protection Agency (EPA) as an NOC, in accordance with Title 40 Code of Federal Regulations (CFR), Part 61, ''National Emission Standards for Hazardous Air Pollutants.'' The information required for submittal to the EPA is specified in 40 CFR 61.07. The potential emissions from this activity are estimated to provide less than 0.1 millirem/year total effective dose equivalent to the hypothetical offsite maximally exposed individual, and commencement is needed within a short time. Therefore, this application also is intended to provide notification of the anticipated date of initial startup in accordance with the requirement listed in …

This Test Plan provides a test method to dedicate the leak detection relays used on the new Pumping and Instrumentation Control (PIC) skids. The new skids are fabricated on-site. The leak detection system is a safety class system per the Authorization Basis.

The Office of Fissile Materials Disposition is currently involved in the development of a comprehensive approach to the long-term storage and disposition of fissile materials. A major objective of this effort is to provide a framework for US efforts to prevent the proliferation of nuclear weapons. This will entail both the elimination of excess highly enriched uranium and plutonium, and the insurance of the highest standards of safety, security, and international accountability. The Office of Fissile Materials Disposition is supporting an Interagency Working Group that has initiated a comprehensive review of alternatives for plutonium disposition which takes into account non-proliferation, economic, technical, institutional, schedule, environmental, and health and safety issues. These alternatives were identified by the development of screening criteria as a guide to the selection of alternatives that best achieve the fissile nuclear material long-term storage and disposition goals of the US Government.

Development testing will be performed on the water jet cleaning fixture to determine the most effective arrangement of water jet nozzles to remove contamination from the surfaces of canisters and other debris. The following debris may be stained with dye to simulate surface contaminates: Mark O, Mark I, and Mark II Fuel Storage Canisters (both stainless steel and aluminum), pipe of various size, (steel, stainless, carbon steel and aluminum). Carbon steel and stainless steel plate, channel, angle, I-beam and other surfaces, specifically based on the Scientific Ecology Group (SEG) inventory and observations of debris within the basin. Test procedure for developmental testing of High Pressure Water Jet System.