The Acceptance Test Procedure for the 241-AN-107 Caustic Addition Mixer Pump Data logger, WHC-SD-WM-ATP-149, was started on September 25, 1995, and completed November 13, 1995. K.G. Carothers of Tank Waste Remediation Engineering requested the test procedure and ICF Kaiser Control Systems Engineering group wrote the test procedure and executed it at the 305 building in 300 area and at the 241-AN Tank Farm in 200 East area. The purpose of this report is to document that the Caustic addition Mixer Pump Data logger, functioned as intended as installed at 241-AN-107 tank farm.

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.

The Virasoro master equation (VME) describes the general affine-Virasoro construction $T=L^abJ_aJ_b+iD^a \dif J_a$ in the operator algebra of the WZW model, where $L^ab$ is the inverse inertia tensor and $D^a $ is the improvement vector. In this paper, we generalize this construction to find the general (one-loop) Virasoro construction in the operator algebra of the general non-linear sigma model. The result is a unified Einstein-Virasoro master equation which couples the spacetime spin-two field $L^ab$ to the background fields of the sigma model. For a particular solution $L_G^ab$, the unified system reduces to the canonical stress tensors and conventional Einstein equations of the sigma model, and the system reduces to the general affine-Virasoro construction and the VME when the sigma model is taken to be the WZW action. More generally, the unified system describes a space of conformal field theories which is presumably much larger than the sum of the general affine-Virasoro construction and the sigma model with its canonical stress tensors. We also discuss a number of algebraic and geometrical properties of the system, including its relation to an unsolved problem in the theory of $G$-structures on manifolds with torsion.

We associate to outer automorphisms of generalized Kac-Moody algebras generalized character-valued indices, the twining characters. A character formula for twining characters is derived which shows that they coincide with the ordinary characters of some other generalized Kac-Moody algebra, the so-called orbit Lie algebra. Some applications to problems in conformal field theory, algebraic geometry and the theory of sporadic simple groups are sketched.

INTEG is a computer program to calculate groundwater contamination concentration levels and human dose from inventories, vadose zone transport, and aquifer transport.

This document includes the calculations needed to quantify the risk associated with unmitigated and mitigated pressurized spray releases from tank farm transfer equipment inside transfer enclosures. The calculations within this document support the spray leak accident analysis reported in the TWRS FSAR.

Ammonia is generated in waste tanks via the degradation of nitrogen compounds. The ammonia is released from the liquids by a mechanism which is dependent on temperature, pH, ionic strength and ammonia concentration. The release of ammonia to the environment occurs via diffusion of ammonia through a stagnant air mass and into the ventilation system.

This report documents the conceptual design review of the sludge offload system for the Spent Nuclear Fuel Project. The design description, drawings, available analysis, and safety analysis were reviewed by a peer group. The design review comments and resolutions are documented.

The purpose of this report is to summarize selected lightning issues concerning the Hanford Waste Tanks. These issues include the probability of a lightning discharge striking the area immediately adjacent to a tank including a riser, the consequences of significant energy deposition from a lightning strike in a tank, and mitigating actions that have been or are being taken. The major conclusion of this report is that the probability of a lightning strike deposition sufficient energy in a tank to cause an effect on employees or the public is unlikely;but there are insufficient, quantitative data on the tanks and waste to prove that. Protection, such as grounding of risers and air terminals on existing light poles, is recommended.

This documentation and analysis for packaging documents that Hardigg cases meet the requirements for Industrial Packaging Type 1 containers for the packaging of low specific activity radioactive material or surface contaminated object quantities for transport.

This document provides the values of dose calculations for radioactive liquid waste tank criticality.

This document is a hard copy of the CY 1995 airborne and liquid effluent data contained in the Environmental Release Summary (ERS) computer database.

The Mixed Waste Focus Area (MWFA) has chartered the Savannah River Technology Center (SRTC) to design and fabricate a Transportable Vitrification System (TVS) to demonstrate treatment of Low-Level Mixed Waste (LLMW). This system will be used to demonstrate the feasibility of vitrification on several LLMW streams. The first stream to be demonstrated will be the Oak Ridge Reservation (ORR) K-25 B&C Pond sludge. Before the demonstrations in the TVS can take place, a surrogate sludge vitrification demonstration had to be performed in the EV-16 melter located at the DOE Industrial Center for Vitrification Research (Center) at the Environmental Systems Engineering Department at Clemson University. During the demonstration at the Center, a 50 wt% B&C sludge glass composition was tested to determine any processing problems. A total of 1510 pounds (686 kg) of glass were produced from 9328 pounds (4240 kg) of surrogate feed. The resulting glass product was homogeneous and very durable.

DWPF-Engineering requested that SRTC determine the minimum indicated melter vapor space temperature that must be maintained in order to minimize the potential for off-gas flammability during a steady sludge-only feeding operation at 1.0 GPM containing 14,000 ppm total organic carbon. The detailed scope of this request is described in the technical task request, HLW-DWPF-TTR-960092 (DWPT Activity No. DWPT-96-0065). In response to this request, a dynamic simulation study was conducted in which the concentration of flammable gases was tracked throughout the course of a simulated 3X off-gas surge using the melter off-gas (MOG) dynamics model. The results of simulation showed that as long as the melter vapor space temperature as indicated on TI4085D is kept at 570 degrees C or higher, the peak concentration of combustible gases in the melter off-gas system is not likely to exceed 60 percent of the lower flammability limit (LFL). The minimum TI4085D of 570 degrees C is valid only when the air purges to FIC3221A and FIC3221B are maintained at or above 850 and 250 lb/hr, respectively. All the key bases and assumptions along with the input data used in the simulation are described in the attached E-7 calculation note.

Probably the single largest advantage of the inertial route to fusion energy (IFE) is the perception that its power plant embodiments could achieve acceptable capacity factors. This is a result of its relative simplicity, the decoupling of the driver and reactor chamber, and the potential to employ thick liquid walls. We examine these issues in terms of the complexity, reliability, maintainability and, therefore, availability of both magnetic and inertial fusion power plants and compare these factors with corresponding scheduled and unscheduled outage data from present day fission experience. We stress that, given the simple nature of a fission core, the vast majority of unplanned outages in fission plants are due to failures outside the reactor vessel itself Given we must be prepared for similar outages in the analogous plant external to a fusion power core, this puts severe demands on the reliability required of the fusion core itself. We indicate that such requirements can probably be met for IFE plants. We recommend that this advantage be promoted by performing a quantitative reliability and availability study for a representative IFE power plant and suggest that databases are probably adequate for this task.

This System Design Requirement document establishes the performance, design, development and test requirements for the Computer System, WBS 1.5.1 which is part of the NIF Integrated Computer Control System (ICCS). This document responds directly to the requirements detailed in ICCS (WBS 1.5) which is the document directly above.

This document provides the preliminary planning basis for the U.S. Department of Energy (DOE) to provide a sufficient quantity of high-level waste feed to the privatization contractor during Phase I. By this analysis of candidate high-level waste feed sources, the initial quantity of high-level waste feed totals more than twice the minimum feed requirements. The flexibility of the current infrastructure within tank farms provides a variety of methods to transfer the feed to the privatization contractor`s site location. The amount and type of pretreatment (sludge washing) necessary for the Phase I processing can be tailored to support the demonstration goals without having a significant impact on glass volume (i.e., either inhibited water or caustic leaching can be used).

This document outlines the steps required to properly document the operability testing of this prototypical system. The tree is deployed in the annulus of the underground nuclear waste storage tank 241-AN-107; it is to monitor the temperature gradient of the primary containment wall using 3 arrays of contact thermocouples.

For the bcc-U-Ti alloy system, H and D solubility measurements have been made on 12 alloy specimens ranging in composition from pure U to pure Ti and temperature range bounded by 900 K to 1,500 K. The results are described by a model within a standard error of 3%.

The overall objective to this two phase program is to investigate dry carbon-based sorbents for mercury control. During Phase I, a bench-scale field test device that can simulate an electrostatic precipitator, a pulse-jet baghouse, or a reverse-gas baghouse will be designed and integrated with an existing pilot-scale facility at Public Service Company of Colorado`s (PSCo`s) Comanche station. Various sorbents will then be injected to determine the mercury removal efficiency for each. During Phase II effort, component integration of the most promising technologies shall be tested at the 5000 acfm pilot-scale. The primary task currently underway is the facility design. The design is expected to be finished in January, 1996. The facility, regardless of the particulate control module configuration, will be fitted with supply line injection port, through which mercury sorbents and SO{sub 2} control sorbents can be added to the flue gas stream.

Shashkov`s method for scalar cell-edge and cell-center variables is derived. Dot products for cell-edge vectors are computed for a corner of the cell. Next, the divergence and gradient are discretized. The diffusion equation is solved with cell-edge continuity and boundary conditions. A symmetric positive definite solution matrix is proven.

This is full revision to Revision 0 of this report. The purpose of this report is to provide a summary of analyses done to support activities performed for single-shell tanks. These activities are encompassed by the flammable gas Unreviewed Safety Question (USQ). The basic controls required to perform these activities involve the identification, elimination and/or control of ignition sources and monitoring for flammable gases. Controls are implemented through the Interim Safety Basis (ISB), IOSRs, and OSDs. Since this report only provides a historical compendium of issues and activities, it is not to be used as a basis to perform USQ screenings and evaluations. Furthermore, these analyses and others in process will be used as the basis for developing the Flammable Gas Topical Report for the ISB Upgrade.

The SmartShelf{trademark} system is designated to maintain an up-to-the-minute inventory of containers or other assets. Through the use of Dallas Semiconductor touch memory devices affixed to containers and entrusted to authorized operators, the system can determine which operator added or removed which container and when the transaction occurred. Through the use of a PC-based data base system, reports of the current status of all containers and nodes can be generated in minutes. This report covers activities on the SmartShelf{trademark} project for the period 1 October 1995 through 30 September 1996. During this year, project team members have advanced the state of the hardware and software from rough prototypes to a working system ready for field trials.The project team has developed an intimate working knowledge of the hardware and software, and has become expert at implementations of Dallas Semiconductor touch memory devices. System hardware includes a desktop PC running LabView and Microsoft Access, and an STD-bus 8086 computer to monitor container storage locations (nodes). The STD-bus computer monitors up to 128 nodes, and responds to operator actions (adding or removing containers) within 10 seconds. The PC uses LabView software to query the STD-bus machine to obtain records of transactions, and to …

This is full revision to Revision 0 of this report. The purpose of this report is to provide a summary of analyses done to support activities performed for double shell tanks. These activities are encompassed by the flammable gas Unreviewed Safety Question (USQ). The basic controls required to perform these activities involve the identification, elimination and/or control of ignition sources and monitoring for flammable gases. Controls are implemented through the Interim Safety Basis (ISB), IOSRs, and OSDs. Since this report only provides a historical compendium of issues and activities, it is not to be used as a basis to perform USQ screenings and evaluations. Furthermore, these analyses and others in process will be used as the basis for developing the Flammable Gas Topical Report for the ISB Upgrade.