This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-BY-112. This report supports the requirements of the Tri-Party Agreement Milestone M-44-10. (This tank has been designated a Ferrocyanide Watch List tank.)

In May of 1996, the US Department of Energy implemented a four-year demonstration project identified as the Hanford Tanks Initiative (HTI). The HTI mission is to minimize technical uncertainties and programmatic risks by conducting demonstrations to characterize and remove tank waste using technologies and methods that will be needed in the future to carry out tank waste remediation and tank farm closure at the Hanford Site. Included in the HTI scope is the development of retrieval performance evaluation criteria supporting readiness to close single-shell tanks in the future. A path forward that includes evaluation of closure basis alternatives has been outlined to support the development of retrieval performance evaluation criteria for the AX Farm, and eventual preparation of the SEIS for AX Farm closure. This report documents the results of the Task 4, Waste Inventory study performed to establish the best-basis inventory of waste contaminants for the AX Farm, provides a means of estimating future soil inventories, and provides data for estimating the nature and extent of contamination (radionuclide and chemical) resulting from residual tank waste subsequent to retrieval. Included in the report are a best-basis estimate of the existing radionuclide and chemical inventory in the AX Farm Tanks, an …

The In-situ Vitrification (ISV) process potentially offers the most stable waste-form for containment of radiologically contaminated soils while minimizing personnel contamination. This is a problem that is extensive, and at the same time unique, to the US Department of Energy`s (DOE) Weapons Complex. An earlier ISV process utilized joule heating of the soil to generate the subsurface molten glass product. However previous test work has indicated that the Savannah river Site soils (SRS) may not be entirely suitable for vitrification by joule heating due to their highly refractory nature. The concept of utilizing a plasma torch for soil remediation by in-situ vitrification has recently been developed, and laboratory test work on a 100 kW unit has indicated a potentially successful application with SRS soils. The Environmental Restoration Division (ERD) of Westinghouse Savannah River Company (WSRC) conducted the first field scale demonstration of this process at the (904-65G) K-Reactor Seepage Basin in October 1996 with the intention of determining the applicability and economics of the process for remediation of a SRS radioactive seepage basin. The demonstration was successful in completing three vitrification runs, including two consecutive runs that fused together adjacent columns of glass to form a continuous monolith. This report …

On the base program, testing was completed at the Tampa Electric Company`s (TECo`s) Big Bend Station in November 1992. The upgrade option tested was DBA additive. Additional testing was conducted at this site during the previous quarter (April through June 1997). Results from that testing were presented in the Technical Progress Report dated July 1997. For Option I, at the Hoosier Energy Merom Station, results from another program co-funded by the Electric Power Research Institute (EPRI) and the National Rural Electric Cooperative Association have been combined with results from DOE-funded testing. Three upgrade options have been tested: DBA additive, sodium formate additive, and high pH set-point operation. All testing was completed by November 1992. There were no activities for this site during the current quarter. Option II involved testing at the Southwestern Electric Power Company Pirkey Station. Both sodium formate and DBA additives were tested as potential upgrade options. All of the testing at this site was completed by May 1993. On Option III, for testing at the PSI Energy Gibson Station, testing with sodium formate additive was completed in early October 1993, and a DBA additive performance and consumption test was completed in March of 1994. There were no …

This Operational Test Report was performed to assure the Isokinetic Stack Effluent Monitoring System (ISEMS) operates in accordance with system design and specifications.

A direct solver method is developed for solving Poisson`s equation numerically for the electrostatic potential {phi}(r,z) in a cylindrical region (r < R{sub wall}, 0 < z < L). The method assumes the charge density {rho}(r,z) and wall potential {phi}(r = R{sub wall}, z) are specified, and {partial_derivative}{phi}/{partial_derivative}z = 0 at the axial boundaries (z = 0, L).

The Hanford Seismic Monitoring Network consists of two designs of equipment and sites: seismometer sites and strong motion accelerometer (SMA) sites. Seismometer sites are designed to locate earthquakes on and near the Hanford Site and determine their magnitude and hypocenter location. The US Department of Energy (DOE) Order 5480.28, Natural Phenomena Hazards (DOE 1993) requires that facilities or sites that have structures or components in Performance Category 2 with hazardous material, and all Performance Category 3 and 4 facilities shall have instrumentation or other means to detect and record the occurrence and severity of seismic events. In order to comply with DOE Order 5480.28, the Hanford Seismic Monitoring Network seismometer sites needed to be complemented with strong motion accelerometers to record the ground motion at specific sites. The combined seismometer sites and strong motion accelerometer sites provide the Hanford Site with earthquake information to comply with DOE Order 5480.28. The data from these instruments will be used by the PHMC staff to assess the damage to facilities following a significant earthquake.

TART97 is a coupled neutron-photon, 3 Dimensional, combinatorial geometry, time dependent Monte Carlo transport code. This code can on any modern computer. It is a complete system to assist you with input preparation, running Monte Carlo calculations, and analysis of output results. TART97 is also incredibly FAST; if you have used similar codes, you will be amazed at how fast this code is compared to other similar codes. Use of the entire system can save you a great deal of time and energy. TART97 is distributed on CD. This CD contains on- line documentation for all codes included in the system, the codes configured to run on a variety of computers, and many example problems that you can use to familiarize yourself with the system. TART97 completely supersedes all older versions of TART, and it is strongly recommended that users only use the most recent version of TART97 and its data riles.

Plans are to close Tank 17, a type IV waste tank in the F-area Tank Farm, by filling it with pumpable backfills. Most of the waste was removed from the tank in the late 1980s, and the remainder of the waste was removed in a short spray washing campaign that began on 11 April 1997. More details on the planned closure can be found in the Closure Plan for the High-Level Waste (HLW) Tanks and the specific closure module for Tank 17. To show that closure of the tank is environmentally sound, a performance evaluation has been performed for Tank 17. The performance evaluation projected the concentration of contaminants at various locations and times after closure. This report documents the basis for the inventories of contaminants that were used in the Tank 17 performance evaluation.

This revision of the APT Waste Management Plan details the waste management requirements and issues specific to the APT plant for design considerations, construction, and operation. The APT Waste Management Plan is by its nature a living document and will be reviewed at least annually and revised as required.

This CSER gives the limits for the storage of one-gallon cans in the hot cells and the SERF in the 327 Building. The 327 Building is used to perform post irradiation testing of fissionable materials in remotely manipulated hot cells. Historically, scrap pieces of fuel cladding, cleanup materials, and other items have been placed into one-gallon paint cans for storage and ultimately disposal. These cans of materials had been assumed to contain no (or essentially no) fissionable materials, and therefore were not specifically controlled for material accountability. Recently, eight cans with high radiation levels were selected to be assayed for content. These cans contained from 0 to 2.5 grams of fissionable material, with an average of 1 gram per can. Since several of the hot cells contained a significant quantity of the cans, concerns were raised as to whether a CPS nonconformance had occurred, and should the cans have some limits for operation placed on them. This analysis is a response to the concerns raised, and gives guidance for incorporating operating limits for the one-gallon waste cans.

For more than three decades Mortandad Canyon has been the primary release area of treated liquid radioactive waste from the Los Alamos National Laboratory (Laboratory). In this survey, six water samples and seven stream sediment samples collected in Mortandad Canyon were analyzed by thermal ionization mass spectrometry (TIMS) to determine the plutonium and uranium activity levels and atom ratios. Be measuring the {sup 240}Pu/{sup 239}Pu atom ratios, the Laboratory plutonium component was evaluated relative to that from global fallout. Measurements of the relative abundance of {sup 235}U and {sup 236}U were also used to identify non-natural components. The survey results indicate the Laboratory plutonium and uranium concentrations in waters and sediments decrease relatively rapidly with distance downstream from the major industrial sources. Plutonium concentrations in shallow alluvial groundwater decrease by approximately 1000 fold along a 3000 ft distance. At the Laboratory downstream boundary, total plutonium and uranium concentrations were generally within regional background ranges previously reported. Laboratory derived plutonium is readily distinguished from global fallout in on-site waters and sediments. The isotopic ratio data indicates off-site migration of trace levels of Laboratory plutonium in stream sediments to distances approximately two miles downstream of the Laboratory boundary.

The mission of the B Plant Transition Project is to place B Plant and its ancillary facilities (referred to as B Plant throughout this document) in a safe and stable condition which requires minimal long term surveillance and maintenance (S&M), thereby reducing the risks associated with the current radiological and chemical inventory and the costs for S&M until disposition. Transition may include activities such as removal of stored radioactive and hazardous materials, safe shutdown of support systems such as electrical circuits and ventilation, and installation of new or modified systems required to support S&M for a 10 year period. The goal of this Project is to complete B Plant transition activities by September 30, 1998. During transition, the Waste Encapsulation and Storage Facility will be isolated from B Plant for stand alone operation. Upon completion of transition, B Plant will be turned over to the Office of Environmental Restoration (EM-40) for the S&M phase of B Plant decommissioning.

Shape overlays provide a means of statically imposing a physical region containing specified material properties onto a zoned mesh. In the most general case, material interface boundaries are unrelated to mesh zone boundaries, causing zones to contain a mixture of materials, and the mesh itself is not uniform in physical space. We develop and apply an algorithm for shape overlays on nonorthogonal, nonuniform meshes in two dimensions. Examples of shape generation in a multiblock uid dynamics code are shown.

The Technique for Human Error Analysis (ATHEANA) is a newly developed human reliability analysis (HRA) methodology that aims to facilitate better representation and integration of human performance into probabilistic risk assessment (PRA) modeling and quantification by analyzing risk-significant operating experience in the context of existing behavior science models. The fundamental premise of ATHEANA is that error-forcing contexts (EFCs), which refer to combinations of equipment/material conditions and performance shaping factors (PSFs), set up or create the conditions under which unsafe actions (UAs) can occur. ATHEANA is being developed in the context of nuclear power plant (NPP) PRAs, and much of the language used to describe the method and provide examples of its application are specific to that industry. Because ATHEANA relies heavily on the analysis of operational events that have already occurred as a mechanism for generating creative thinking about possible EFCs, a database, called the Human Events Reference for ATHEANA (HERA), has been developed to support the methodology. Los Alamos National Laboratory`s (LANL) Human Factors Group has recently joined the ATHEANA project team; LANL is responsible for further developing the database structure and for analyzing additional exemplar operational events for entry into the database. The Action Characterization Matrix (ACM) is …

Optimization of molecular detection efficiencies is important for analytical applications of single molecule detection methods. In microdroplets some experimental limitations can be reduced, primarily because the molecule cannot diffuse away from the excitation and collection volume. Digital molecular detection using a stream of microdroplets has been proposed as a method of reducing concentration detection limits by several orders of magnitude relative to conventional measurements. However, the bending and reflection of light at the microdroplet`s liquid-air interface cause the illumination intensity and fluorescence intensity collected to be strongly dependent on the position of the molecule within the droplet. The goal is to model the detection of single molecules in microdroplets so that one can better understand and optimize detection efficiencies. In the first year of this modeling effort the authors studied the collection of fluorescence from unit-amplitude dipoles inside of spheres. In this second year they modified their analysis to accurately model the effects of excitation inhomogeneities, including effects of molecular saturation, motion of the droplet, and phase variations between the two counter-propagating waves that illuminate the droplet. They showed that counter-propagating plane wave illumination can decrease the variations in the intensity which excites the molecules. Also in this second year …

Pollution Prevention/Waste Minimization (P2/WMin) is the Department of Energy`s preferred approach to environmental management. The P2/WMin mission is to eliminate or minimize waste generation, pollutant releases to the environment, use of toxic substances, and to conserve resources by implementing cost-effective pollution prevention technologies, practices, and polices.

This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-AP-105. This report supports the requirements of the Tri-Party Agreement Milestone M 44-05.

The purpose of this document is to provide a single referenceable document that provides the X/Qs for the solid waste facilities in the 200 Area, that is to provide the X/Qs for the Solid Waste Dispersal Facilities Master Safety Analysis Report (WHC-SD-WM-MSAR-001, REV. 0, 1996). The X/Qs will be used for the radiological dose estimates in the accident safety analyses. Thus, this document is also to provide the information necessary to perform bounding estimates of the radiological consequences for hypothetical accidents for various solid waste facilities. This document is to examine the variations in the plume dispersion factors associated with the various solid waste facilities. Specifically examined are X/Qs associated with different receptors located in different sectors and at different distances. Examination of one facility included a large area X/Q, while examination of another facility included an elevated release. Generally, the X/Qs are determined for ground releases with and without building wake. In addition, sensitivity of how plume characteristics were affected by using different meteorological data was examined. Each receptor described in this document was evaluated for both 99.5% and 50% meteorological data. Attributes such as plume meander, plume rise, settling and wash-out are not considered in this document.

Recycled Type 304 stainless steel from both Carolina Metals Inc. (CMI) and Manufacturing Science Corporation (MSC) met all the requirements of ASTM A-240 required by Procurement Specification G-SPP-K-00005 Rev. 4. Mechanical strength and corrosion resistance of the material are adequate for service as burial boxes, overpacks, and drums. Inclusion content of both manufacturer`s material was high, resulting in a corresponding decrease in the corrosion resistance. Therefore, an evaluation of the service conditions should be performed before this material is approved for other applications. These heats of stainless steel are not suitable for fabricating DWPF glass canisters because the inclusion and carbon contents are high. However, MSC has recently installed a vacuum induction furnace capable of producing L grade material with a low inclusion content. Material produced from this furnace should be suitable for canister material if appropriate care is taken during the melting/casting process.

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With the end of the Cold War, the Strategic Arms Reduction Treaties (START), and other agreements, the United States and Russia have dramatically reduced their arsenals of nuclear weapons. As a result, each side has accumulated large stockpiles of plutonium, one of the principal materials used in nuclear warheads. The United States recently declared a holding of approximately 50 metric tons of weapons-usable plutonium excess to military needs. Even greater levels are believed to exist in Russia.

The Fischer-Tropsch (F-T) reaction provides a way of converting coal-derived synthesis gas (CO and H{sub 2}) to liquid fuels. Since the reaction is highly exothermic, one of the major problems in control of the reaction is heat removal. Recent work has shown that the use of slurry bubble column reactors (SBCRs) can largely solve this problem. Iron-based (Fe) catalysts are preferred catalysts for F-T when using low CO/H{sub 2} ratio synthesis gases derived from modern coal gasifiers. This is because in addition to reasonable F-T activity, the F-T catalysts also possess high water gas shift (WGS) activity. However, a serious problem with the use of Fe catalysts in a SBCR is their tendency to undergo attrition. This can cause fouling/plugging of downstream filters and equipment, making the separation of catalyst from the oil/wax product very difficult if not impossible, and results in a steady loss of catalyst from the reactor. The objectives of this research are to develop a better understanding of the parameters affecting attrition resistance of Fe F-T catalysts suitable for use in SBCRs and to incorporate this understanding into the design of novel Fe catalysts having superior attrition resistance. Catalyst preparations will be based on the use …

This report concerns the packaging configurations being tested by the U.S. DOE and its contractors, and according to U.S. DOT specification 7A Type A (DOT-7A) requirements. The objective of this Test Plan is to describe the testing for the qualification of the M-100 Container, Model M-101/7A/12/90 as a DOT-7A Type A packaging. This packaging system is designed to ship Type A solid radioactive materials, normal form, Form Number 1, Form Number 2, and Form Number 3.