[en] This document contains ALARACT Demonstrations identifying agreements made between LMHC, FDH, DOE-RL, and the Washington State Department of Health for frequently performed work activities in TWRS. These ALARACTs do not cover new activities, modifications, construction, or decontamination and decommissioning activities

[en] Contaminated high-efficiency particulate air (HEPA) filter media, containing PuO₂ powder which had been calcined at 700⁰C, were treated with concentrated H₂SO₄-HNO₃ at 190 to 200⁰C for periods ranging from 0.5 to 2.0 hours. When followed by a dilute HNO₃ rinse, this treatment was shown to be very effective as a plutonium recovery operation (approximately greater than 97% of the plutonium was solubilized). A proposed treatment scheme is given which could provide both a plutonium recovery option for HEPA filters and a reduction in overall waste volume

[en] The Engineering Review Group (ERG) was established by the Office of Nuclear Waste Isolation (ONWI) to help evaluate engineering-related issues in the US Department of Energy's nuclear waste repository program. The August 1985 meeting of the ERG reviewed the Salt Repository Project (SRP) salt irradiation effects program. This report documents the ERG's comments and recommendations on these subjects and the ONWI response to the specific points raised by the ERG

[en] Type 304 stainless steel was heat treated for short times near its melting point in order to determine its microstructural response to thermal cycles typical of the near heat-affected zones of welding processes. The material was rapidly solidified as a powder by centrifugal atomization in a helium environment and consolidated by hot extrusion. Along with the ingot metallurgy material used for canning the powder prior to hot extrusion, it was heat treated using a Gleeble at temperatures of 1200 and 1300 degree C for times ranging from <1 to 1000 s, and the samples were examined for microstructure and the existence of porosity due to entrapped helium. At higher test temperatures and longer treatment times, the material developed extensive porosity, which was stabilized by the presence of helium and which may also have a role in anchoring grain boundaries and inhibiting grain growth. The powder material. At lower test temperatures and shorter treatment times, grain growth in the γ phase appeared to be restricted in the powder material, possible by the presence of helium. An intermediate temperatures and times, a γ-δ duplex microstructure also restricted grain growth again occurred in the δ microstructure. 9 refs., 14 figs., 3 tabs

[en] The Savannah River Plant (SRP) will license and construct an underground repository in salt for HLW and DHLW. Waste package performance requirements are an essentially complete containment of radioactivity in the waste package for a period of 300 to 1000 years, and a controlled or limited release of radioactivity from the waste package and the engineered barrier system. Performance requirements are trivial unless the waste package is contacted by fluids. An advantage of a salt repository is its dryness, with limited fluids available for interactions with emplaced waste packages. The fluids that are present in salt (saturated brine solutions) are aggressive toward some of the waste package components. The fluids that might contact the emplaced waste package are water inflow due to failure of the sealing system, human intrusion, etc. Such fluids are referred to as ''intrusion brines'' and are generally expected to be NaCl-type brines. Water present in the salt include chemically bound water found in various minerals and clays, ''free'' or sorbed water (e.g., in clays), and brine inclusions. Solubilities of brine constituents generally increase with temperature

[en] The purpose of this strategy is to identify the Fiscal Year (FY) 2001 Hanford Site waste reduction, sanitary recycling and affirmative procurement goals and identify the action required to ensure that the Secretary of Energy's FY 2005 pollution prevention and the FY 2001 Hanford Site goals are met. The strategy and plan to ensure that the Secretary of Energy's routine waste reduction, recycling, cleanup/stabilization waste and affirmative procurement goals are met consists of four phases. The first phase is to ensure that the infrastructure is in place to support planning and organization. This phase involves ensuring that roles and responsibilities are identified; requirement documents are current; goals and successes are communicated; and accurate and current waste information is available. Roles and responsibilities are identified and the RL requirement documents (i.e., the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan and Hanford Site Guide for Preparing and Maintaining Generator Group Pollution Prevention Program Documentation) will specify the Secretary of Energy's goals. Goals will be communicated formally and informally via the Hanford Reach, training sessions, meetings and correspondence. Sharing of pollution prevention successes and goal progress are encouraged at the Pollution Prevention/Waste Minimization (PZ/WMin) quarterly meetings. Existing site waste generation databases will be utilized to provide current waste generation data. The second phase of the strategy and plan is to establish and allocate goals by prime contractor (i.e. Fluor Hanford, Inc. (FH), Pacific Northwest National Laboratory (PNNL), Bechtel Hanford Inc. (BHI), and CH2MHill Hanford Group (CHG)). This requires determining current status toward meeting the Secretary of Energy's goals; establishing the Hanford Site FY goals, and allocating waste reduction goals by prime contractor. The third phase of the strategy and plan is goal implementation. This phase involves the identification and implementation of corrective actions for problem areas identified either during the development of the Hanford Site goals or during monthly monitoring of the goals. Areas of concern identified during the development of the goals were the Mixed Low Level Waste (MLLW), Hazardous, and cleanup waste goal. The fourth phase of the strategy and plan is measuring results. This phase consists of: Measuring Results; Development of performance measures; and Reporting progress quarterly. The performance measures have been developed for the tracking of the waste reduction, sanitary recycling, affirmative procurement, and toxic chemical release goals. The first quarter performance measures tracking the recommended goals will be issued by January 3 I, 2001

[en] 'The research objective was to test and develop optical methods for real-time, remote and in-situ testing of corrosion processes on the surface of vitrified nuclear wastes. This report summarizes the research conducted in the first 1.5 years of a 3 year grant. At this point, the authors have identified the conditions for optimal tests and demonstrated that both IR reflection and Raman spectroscopies can be used to determine the dealkalization process in the surface of simple glasses in real time.'

[en] This paper examines volume reduction options that are now or soon will be available for low-level wastes. These wastes generally are in the form of combustible solids, noncombustible solids, and wet wastes (solid/liquid). Initially, the wastes are collected and stored onsite. Preconditioning may be required, e.g., sorting, shredding, and classifying the solids into combustible and noncombustible fractions. The volume of combustible solids can be reduced by compaction, incineration/pyrolysis, acid digestion, or molten salt combustion. Options for reducing the volume of noncombustible solids include compaction, size reduction and decontamination, meltdown-casting, dissolution and electropolishing. Burnable wet wastes (e.g., organic wastes) can be evaporated or combusted; nonburnable wet wastes can be treated by various evaporative or nonevaporative processes. All radioactive waste processing operations result in some equipment contamination and the production of additional radioactively contaminated wastes (secondary wastes). 23 figures

[en] Throughout the three-year project funded by the Department of Energy (DOE) and lead by Virginia Tech (VT), project tasks were modified by consensus to fit the changing needs of the DOE with respect to developing new inert matrix fuel processing techniques. The focus throughout the project was on the use of microwave energy to sinter fully stabilized zirconia pellets using microwave energy and to evaluate the effectiveness of techniques that were developed. Additionally, the research team was to propose fundamental concepts as to processing radioactive fuels based on the effectiveness of the microwave process in sintering the simulated matrix material.

[en] A scoping study has been undertaken to determine the state-of-the-art of waste segregation technology as applied to the management of low-level waste (LLW). Present-day waste segregation practices were surveyed through a review of the recent literature and by means of personal interviews with personnel at selected facilities. Among the nuclear establishments surveyed were Department of Energy (DOE) laboratories and plants, nuclear fuel cycle plants, public and private laboratories, institutions, industrial plants, and DOE and commercially operated shallow land burial sites. These survey data were used to analyze the relationship between waste segregation practices and waste treatment/disposal processes, to assess the developmental needs for improved segregation technology, and to evaluate the costs and benefits associated with the implementation of waste segregation controls. For improved processing and disposal of LLW, it is recommended that waste segregation be practiced wherever it is technically feasible and cost-effective to do so. It is noted that LLW management practices are now undergoing rapid change such that the technology and requirements for waste segregation in the near future may differ significantly from those of the present day