The Academy of Natural Sciences of Philadelphia has been conducting biological and water quality studies of the Savannah River since 1951. These studies are designed to assess potential effects of Savannah River Site (SRS) contaminants and warm-water discharges on the general health of the river and its tributaries. The study design includes multiple biological groups spanning a broad range of ecological roles, both because no single group is the best indicator of every component of water quality and because there is wide-spread agreement that protecting the entire system is important.

The 2001 Wastewater Land Application Site Performance Reports for the Idaho National Engineering and Environmental Laboratory describe site conditions for the facilities with State of Idaho Wastewater Land Application Permits. Permit-required monitoring data are summarized, and any permit exceedences or environmental impacts relating to the operation of any of the facilities during the 2001 permit year are discussed. Additionally, any special studies performed at the facilities, which related to the operation of the facility or application of the wastewater, are discussed.

The 2001 Wastewater Land Application Site Performance Reports for the Idaho National Engineering and Environmental Laboratory describe site conditions for the facilities with State of Idaho Wastewater Land Application Permits. Permit-required monitoring data are summarized, and any permit exceedences or environmental impacts relating to the operation of any of the facilities during the 2001 permit year are discussed. Additionally, any special studies performed at the facilities, which related to the operation of the facility or application of the wastewater, are discussed.

Emphasis was placed on current unpublished research and discussion of the future target areas in this field.

In tokamaks, the strong dependence on the toroidal magnetic field of both plasma pressure and energy confinement is what makes possible the construction of small and relatively inexpensive burning plasma experiments using high-field resistive coils. On the other hand, the toroidal magnetic field of tokamaks using superconducting coils is limited by the critical field of superconductivity. In this article, we examine the relative merit of raising the magnetic field of a tokamak plasma by increasing its aspect ratio at a constant value of the peak field in the toroidal magnet. Taking ITER-FEAT as an example, we find that it is possible to reach thermonuclear ignition using an aspect ratio of approximately 4.5 and a toroidal magnetic field of 7.3 T. Under these conditions, fusion power density and neutron wall loading are the same as in ITER [International Thermonuclear Experimental Reactor], but the normalized plasma beta is substantially smaller. Furthermore, such a tokamak would be able to reach an energy gain of approximately 15 even with the deterioration in plasma confinement that is known to occur near the density limit where ITER is forced to operate.

Los Alamos National Laboratory (LANL) has completed experiments involving 15 each, 250- liter experimental test containers of transuranic (TRU) heterogeneous waste immersed in two types of brine similar to those found in the underground portion of the Waste Isolation Pilot Plant (WIPP). To dispose of the waste without removing the brine from the test containers, LANL added commercially available cross-linked polyacrylate granules to absorb the 190 liters of brine in each container, making the waste compliant for shipping to the WIPP in a Standard Waste Box (SWB). Prior to performing the absorption, LANL and the manufacturer of the absorbent conducted laboratory and field tests to determine the ratio of absorbent to brine that would fully absorb the liquid. Bench scale tests indicated a ratio of 10 parts Castile brine to one part absorbent and 6.25 parts Brine A to one part absorbent. The minimum ratio of absorbent to brine was sought because headspace in the containers was limited. However, full scale testing revealed that the ratio should be adjusted to be about 15% richer in absorbent. Additional testing showed that the absorbent would not apply more than 13.8 kPa pressure on the walls of the vessel and that the absorbent …

Certain categories of mixed wastes that contain recoverable amounts of natural uranium can be processed for the recovery of valuable uranium, alone or together with other metals, at licensed uranium mills, and the resulting tailings permanently disposed of as 11e.(2) byproduct material in the mill's tailings impoundment, as an alternative to treatment and/or direct disposal at a mixed waste disposal facility. This paper discusses the regulatory background applicable to hazardous wastes, mixed wastes and uranium mills and, in particular, NRC's Alternate Feed Guidance under which alternate feed materials that contain certain types of mixed wastes may be processed and disposed of at uranium mills. The paper discusses the way in which the Alternate Feed Guidance has been interpreted in the past with respect to processing mixed wastes and the significance of recent changes in NRC's interpretation of the Alternate Feed Guidance that sets the stage for a broader range of mixed waste materials to be processed as alternate feed materials. The paper also reviews the le gal rationale and policy reasons why materials that would otherwise have to be treated and/or disposed of as mixed waste, at a mixed waste disposal facility, are exempt from RCRA when reprocessed as alternate …

This project is concerned with the research and development of a technique to manipulate small particles using acoustic energy coupled into a fluid filled plastic or glass sample chamber. These resulting miniaturized systems combine high functionality with an inexpensive, disposable sample chamber. Our approach to this problem is based on a combination of sophisticated modeling tools in conjunction with laboratory experiments. The design methodology is summarized in Figure 1. The process begins by investigating a wide range of device parameters using a one-dimensional analytical approximation. The results of these initial parameter studies are incorporated into a sophisticated three-dimensional multi-physics finite element code. From these simulations the optimized designs are prototyped and experimentally tested. The results of the experimental observations are then used to improve analytical approximations and the process is repeated as necessary.

Today's restrictive environmental regulations encourage paper mills to close their water systems. Closed water systems increase the level of contaminants significantly. Accumulations of solid suspensions are detrimental to both the papermaking process and the final products. To remove these solids, technologies such as flotation using dissolved air (DAF), centrifuging, and screening have been developed. Dissolved Air Flotation systems are commonly used to clarify whitewater. These passive systems use high pressure to dissolve air into whitewater. When the pressure is released, air micro-bubbles form and attach themselves to fibers and particles, which then float to the surface where they are mechanically skimmed off. There is an economic incentive to explore alternatives to the DAF technology to drive down the cost of whitewater processing and minimize the use of chemicals. The installed capital cost for a DAF system is significant and a typical DAF system takes up considerable space. An alternative approach, which is the subject of this project, involves a dual method combining the advantages of chemical flocculation and in-line ultrasonic clarification to efficiently remove flocculated contaminants from a water stream

The first remote-handled transuranic (RH-TRU) waste is expected to be permanently disposed of at the Waste Isolation Pilot Plant (WIPP) during Fiscal Year (FY) 2003. The first RH-TRU waste shipments are scheduled from the Battelle Columbus Laboratories (BCL) to WIPP in order to facilitate compliance with BCL Decommissioning Project (BCLDP) milestones. Milestones requiring RH-TRU waste containerization and removal from the site by 2004 in order to meet a 2006 site closure goal, established by Congress in the Defense Facilities Closure Projects account, necessitated the establishment and implementation of a site-specific program to direct the packaging of BCLDP RH-TRU waste prior to the finalization of WIPP RH-TRU waste characterization requirements. The program was designed to collect waste data, including audio and videotape records of waste packaging, such that upon completion of waste packaging, comprehensive data records exist from which compliance with final WIPP RH-TRU waste characterization requirements can be demonstrated. With the BCLDP data records generated to date and the development by the U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) of preliminary documents proposing the WIPP RH-TRU waste characterization program, it is possible to evaluate the adequacy of the BCLDP program with respect to meeting proposed characterization objectives. The BCLDP …

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The activities of the Advanced Gas Turbine Systems Research (AGTSR) program for this reporting period are described in this quarterly report. The report is divided into discussions of Membership, Administration, Technology Transfer (Workshop/Education), Research and Miscellaneous Related Activity. Items worthy of note are presented in extended bullet format following the appropriate heading.

The objective of the Advanced High-Temperature Reactor (AHTR) is to provide the very high temperatures necessary to enable low-cost (1) efficient thermochemical production of hydrogen and (2) efficient production of electricity. The proposed AHTR uses coated-particle graphite fuel similar to the fuel used in modular high-temperature gas-cooled reactors (MHTGRs), such as the General Atomics gas turbine-modular helium reactor (GT-MHR). However, unlike the MHTGRs, the AHTR uses a molten salt coolant with a pool configuration, similar to that of the PRISM liquid metal reactor. A multi-reheat helium Brayton (gas-turbine) cycle, with efficiencies >50%, is used to produce electricity. This approach (1) minimizes requirements for new technology development and (2) results in an advanced reactor concept that operates at essentially ambient pressures and at very high temperatures. The low-pressure molten-salt coolant, with its high heat capacity and natural circulation heat transfer capability, creates the potential for (1) exceptionally robust safety (including passive decay-heat removal) and (2) allows scaling to large reactor sizes [{approx}1000 Mw(e)] with passive safety systems to provide the potential for improved economics.

We present here computer modeling efforts to describe the time-dependent pressurization and gas-phase mole fractions inside sealed canisters containing actinide materials packaged with small (0.12 - 0.5 wt. %) amounts of water. The model is run using Chemkin software, and the chemical reaction mechanism includes gas generation due to radiolysis of adsorbed water, interfacial chemical reactions, and adsorption/desorption kinetics of water on PuO2 materials. The ultimate goal is to provide a verifiable computer model that can be used to predict problematic gas generation in storage forms and assure design criteria for short-term storage and transportation of less than well-characterized (with respect to gas generation) material classes. Our initial efforts are intended to assess pressurization and gas-phase mole fractions using well-defined 3013 container test cases. We have modeled gas generation on PuO2 with water loading up to 0.5 wt. %, at 300 and 525 K, for time frames of 3 years. Estimates of the initial H2 generation rates were determined using RadCalc and employed in the Chemkin model to assess time- and coverage-dependent system behavior. Results indicate that canister pressurization due to radiolysis is a relatively slow process, with pressure increases at 300 K of approximately 1.5 atm. for 5000 g …

The overall objective of this project is to demonstrate that a development program based on advanced reservoir management methods can significantly improve oil recovery at the Nash Draw Pool (NDP). The plan includes developing a control area using standard reservoir management techniques and comparing its performance to an area developed using advanced reservoir management methods. Specific goals are (1) to demonstrate that an advanced development drilling and pressure maintenance program can significantly improve oil recovery compared to existing technology applications and (2) to transfer these advanced methodologies to oil and gas producers in the Permian Basin and elsewhere throughout the U.S. oil and gas industry.

In July 2001, the Augusta Newsprint Company partnered with Invensys' Pacific Simulation group to implement an advanced quality control (AQC) solution for the thermomechanical pulping (TMP) process at Augusta Newsprint's Augusta, Georgia, site. The goal of the project is to decrease energy and raw material costs while maintaining final pulp quality. The project involves coordinating AQC in 3 areas of the paper mill to reduce the amount of energy required for manufacturing. In addition, a time-of-day production (TODP) feature will use current power market pricing data to adjust production rates in the pulping operation to minimize the average cost of purchased energy. The AQC implementation is currently in progress.

Building public trust and confidence through openness is a goal of the DOE Carlsbad Field Office for the Waste Isolation Pilot Plant (WIPP). The objective of the virtual document described in this paper is to give the public an overview of the waste characterization steps, an understanding of how waste characterization instrumentation works, and the type and amount of data generated from a batch of drums. The document is intended to be published on a web page and/or distributed at public meetings on CDs. Users may gain as much information as they desire regarding the transuranic (TRU) waste characterization program, starting at the highest level requirements (drivers) and progressing to more and more detail regarding how the requirements are met. Included are links to: drivers (which include laws, permits and DOE Orders); various characterization steps required for transportation and disposal under WIPP's Hazardous Waste Facility Permit; physical/chemical basis for each characterization method; types of data produced; and quality assurance process that accompanies each measurement. Examples of each type of characterization method in use across the DOE complex are included. The original skeleton of the document was constructed in a PowerPoint presentation and included descriptions of each section of the waste …

This paper describes the organization, planning and initial implementation of a DOE OST program to deploy proven, cost effective technologies into D&D programs throughout the complex. The primary intent is to accelerate closure of the projects thereby saving considerable funds and at the same time being protective of worker health and the environment. Most of the technologies in the ''toolkit'' for this program have been demonstrated at a DOE site as part of a Large Scale Demonstration and Deployment Project (LSDDP). The Mound Tritium D&D LSDDP served as the base program for the technologies being deployed in this project but other LSDDP demonstrated technologies or ready-for-use commercial technologies will also be considered. The project team will evaluate needs provided by site D&D project managers, match technologies against those needs and rank deployments using a criteria listing. After selecting deployments the project will purchase the equipment and provide a deployment engineer to facilitate the technology implementation. Other cost associated with the use of the technology will be borne by the site including operating staff, safety and health reviews etc. A cost and performance report will be prepared following the deployment to document the results.

The removal of uranium-233 (233 U) from the auxiliary charcoal bed (ACB) of the Molten Salt Reactor Experiment (MSRE), performed from January through May 2001, created both unique radiological challenges and widely-applicable lessons learned. In addition to the criticality concerns and alpha contamination, 233U has an associated intense gamma photon from the cocontaminant uranium-232 (232U) decaying to thallium-208 (208Tl). Therefore, rigorous contamination controls and significant shielding were implemented. Extensive, timed mock-up training was also imperative to minimize individual and collective personnel exposures. Back-up shielding and containment techniques (that had been previously developed for defense in depth) were used successfully to control significant, changed conditions. Additional controls were placed on tests and on recovery designs to assure a higher level of safety throughout the removal operations. This paper delineates the manner in which each difficulty was solved, while relating the relevance of the results and the methodology to other projects with high dose-rate, highly-contaminated ionizing radiation hazards. Because of the distinctive features of and current interest in molten salt technology, a brief overview is provided. Also presented is the detailed, practical application of radiological controls integrated into, rather than added after, each evolution of the project--thus demonstrating the broad-based benefits of …

The first AlGaAsSb/GaSb quarter-wave distributed Bragg reflectors grown by metallic vapor phase epitaxy are reported. The peak reflectance is 96% for a 10-period structure.

Several different types of sorbents have been synthesized and submitted to WSRC for testing in the removal of Sr and several actinides from Savannah River nuclear waste solutions. Results of screening tests at the Savannah River Site showed that the nonatitanate samples exhibited as good, or better, performance than the monosodium titanate samples proposed for the treatment process.

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The Waste Isolation Pilot Plant (WIPP) is operating under a Resource Conservation and Recovery Act (RCRA) Hazardous Waste Facility Permit (HWFP) for contact-handled (CH) transuranic (TRU) waste. The HWFP contains limitations on allowable emissions from waste disposed in the underground. This environmental performance standard imposed on the WIPP consists of limiting volatile organic compound (VOC) emissions from emplaced waste to ensure protection of human health and the environment. The standard is currently met by tracking individual waste container headspace gas concentrations, which are determined by headspace gas sampling and analysis of CH TRU waste containers. The WIPP is seeking a HWFP modification to allow the disposal of remote-handled (RH) TRU waste. Because RH TRU waste is limited to approximately 5% of the waste volume and is emplaced in the disposal room walls, it is possible to bound the potential RH TRU waste contribution to VOC emissions using conservative upper bounds. These conservative upper bounds were developed as an alternative to RH TRU waste canister headspace gas sampling and analysis. The methodology used to perform the calculations used to evaluate VOC emissions from emplaced RH TRU waste canisters applied the same equations as those used to evaluate VOC emissions in the …

High level waste Evaporators at the Savannah River Site (SRS) process radioactive waste to concentrate supernate and thus conserve tank space. In June of 1997, difficulty in evaporator operation was initially observed. This operational difficulty evidenced itself as a plugging of the evaporator's gravity drain line (GDL). The material blocking the GDL was determined to be a sodium aluminosilicate. Following a mechanical cleaning of the GDL, the evaporator was returned to service until October 1999. At this time massive deposits were discovered in the evaporator pot. As a result of the changes in evaporator chemistry and the resulting formation of aluminosilicate deposits in the evaporator, a comprehensive research and development program has been undertaken. This program is underway in order to assist in understanding the new evaporator chemistry and gain insight into the deposition phenomena. Key results from testing in FY01 have demonstrated that the chemistry of the evaporator feed favors aluminosilicate formation. Both the reaction kinetics and particle growth of the aluminosilicate material under SRS evaporator conditions has been demonstrated to occur within the residence times utilized in the SRS evaporator operation. Batch and continuous-flow experiments at known levels of supersaturation have shown a significant correlation between the deposition …