The two Hanford K Basins are water-filled concrete pools that contain over 2,100 metric tons of N Reactor fuel elements stored in aluminum or stainless steel canisters. During the time the fuel has been stored, approximately 50 m3 of heterogeneous solid material have accumulated in the basins. This material, referred to as sludge, is a mixture of fuel corrosion products, metallic bits of spent fuel and zirconium clad iron and metal corrosion products and silica from migrating sands. Some of the sludges also contain PCBs. The congener group of PCBs was identified as Aroclor 1254. The maximum concentration of sludge PCBS was found to be 140 ppm (as settled wet basis). However, the distribution of the PCBs is non-uniform throughout the sludge (i.e., there are regions of high and low concentrations and places where no PCBs are present). Higher concentrations could be present at various locations. Aroclors 1016/1242, 1221, 1248, 1254, and 1260 were identified and quantified in K West (KW) Canister sludge. In some of these samples, the concentration of 1260 was higher than 1254. The sludge requires pre-treatment to meet tank farm waste acceptance criteria, Among the numerous requirements, the sludge should be retreated so that it does …

This assessment describes the potential Year 2000 (Y2K) problems and describes the methods for achieving Y2K Compliance for Project W-420, Ventilation Stack Monitoring Systems Upgrades. The purpose of this assessment is to give an overview of the project. This document will not be updated and any dates contained in this document are estimates and may change. The project work scope includes upgrades to ventilation stacks and generic effluent monitoring systems (GEMS) at the 244-A Double Contained Receiver Tank (DCRT), the 244-BX DCRT, the 244-CR Vault, tanks 241-C-105 and 241-C-106, the 244-S DCRT, and the 244-TX DCRT. A detailed description of system dates, functions, interfaces, potential Y2K problems, and date resolutions can not be described since the project is in the definitive design phase, This assessment will describe the methods, protocols, and practices to ensure that equipment and systems do not have Y2K problems.

This assessment describes the potential Year 2000 (Y2K) problems and describes the methods for achieving Y2K Compliance for Project W-519, Tank Waste Remediation System Privatization Phase I Infrastructure Support. The purpose of this assessment is to give an overview of the project. This assessment will describe the methods, protocols, and practices to assure that equipment and systems do not have Y2K problems. This document will not be updated and any dates contained in this document are estimates and may change. The scope of project W-519 is to provide utilities and infrastructure to support construction and operation of the private contractor's facility to treat, immobilize, and dispose of tank waste. The private contractor's facility will be located on east side of 200E-area and north of Route 4s (near the defunct grout vaults). The utilities include potable and process water, construction and operational electrical power systems, and liquid effluent disposal transfer lines to the existing effluent treatment facility (ETF) and the liquid effluent retention facility (LERF).

The Mark 22 assemblies previously charged to the P Reactor as the P-11 charge, but never irradiated, are stored in borated racks in Building 105-K Assembly Area. The assemblies are stored inside aluminum cans into which they are placed and subsequently dried upon removal from the P-Reactor. This report discusses non-destructive examinations supplemented by destructive examination of a small number of these assemblies made to establish the acceptability of these assemblies for use as the K-15 charge.

The Mark 22 assemblies previously charged to the P Reactor as the P-11 charge, but never irradiated, are stored in borated racks in Building 105-K Assembly Area. The assemblies are stored inside aluminum cans into which they are placed and subsequently dried upon removal from the P-Reactor. This report discusses non-destructive examinations supplemented by destructive examination of a small number of these assemblies made to establish the acceptability of these assemblies for use as the K-15 charge.

The principal effort has been concentrated on the preparation of clean clinoptilolite, quartz, and boehmite and then reaction of the natural clinoptilolite solid solution to the Naendmember, plus measurements of the endmember solubility to derive an accurate equilibrium constant for the clinoptilolite dissolution reaction, correctly speciated. We are very pleased with the consistency between the best calorimetrically measured and modeled equilibrium constants and those we have determined from 125{degrees}C to 265{degrees}C. These results now provide a basis for relating measurements of reaction rates to departures from equilibrium.

The Basic Research Opportunities in Photovoltaics Workshop was held on May 3, 1999, in Seattle, Washington, in conjunction with the 195th Meeting of the Electrochemical Society. The workshop was structured into eight topics. Each topic area opened with a presentation in which the participants were asked to address the following: a brief introduction of the area of research; key research issues that were identified in an earlier workshop in 1992; what fundamental research has been done since then or is currently being done to address those issues; what are the research issues that are still relevant in light of advances made since the first workshop; identification of new fundamental research opportunities that will lead to important advances and innovations; and identification of significant commonalities and common research issues that have a cross-cutting impact, such as logically exist in silicon-based thin films, II-VI, and related materials. The topic areas discussed included amorphous and microcrystalline silicon, crystalline silicon, cadmium telluride, copper indium diselenide; III-V materials; novel materials and energy conversion approaches, semiconducting oxides, and characterization. After the meeting, participants in each working topic continued discussions by electronic means, completing journal articles that are to be published as a separate section in the …

This report presents preliminary results of laboratory testing of a small block sample of Topopah Spring Tuff. This is the first in a series of tests on small block samples. The purpose of these tests is to investigate the thermal-mechanical, thermal-hydrological, and thermal-chemical response of the rock to conditions similar to the near-field environment (NFE) of a potential nuclear waste repository. This report presents preliminary results of deformation and elastic- wave velocity measurements on a 0.5-m scale block of Topopah Spring tuff tested in uniaxial compression and at temperatures to 85{degrees}C.

Radioactive liquid and semisolid waste from operation of Hanford's nuclear fuel processing plants is stored in 177 underground storage tanks located in the 200 Areas of the Hanford site. 28 of these tanks are of double-shell construction. The remaining 149 tanks are of single-shell construction. Only the newer, double-shell tanks (DST) can meet current requirements for containment of dangerous waste. Therefore, the single-shell tanks (SST) are being ''interim stabilized,'' which is the process of removing liquid from the waste through the use of a jet pump installed in a saltwell which penetrates the waste. Lockheed Martin Hanford Company has decided to purchase additional Pumping and Instrumentation Control (PIC) skids to monitor and control the operation of saltwell jet pumps in SSTs. Similar PIC skids are already in use at several locations. The PIC skids will shut off all power to equipment/instruments if preset limits are exceeded for such conditions as flammable gas, leak detection, pressure and flow, as well as provide air and water necessary for saltwell pumping activities. This document outlines the functional design criteria for pumping and instrumentation control (PIC) skids to support the interim stabilization effort for saltwell pumping.

The calculations in Appendix A and B determine the adequacy of the ramps and platforms to accomplish two tasks: (1) Core sampling using the modifications imposed by the use of a FDNW foundation at PFP; and (2) Core sampling within the 200E and 200W Tank Farms without the imposed modifications. The calculations in this document determined that the ramps and platforms are adequate for use with core sampling equipment when sampling either tank 241-2-361 or within 200E or 200W Tank Farms. When sampling tank 241-2-361 the modifications made by ECN 651132 must be implemented. These modifications are the addition of diagonal cross bracing on both the lateral and longitudinal sides. Also, a 1 1/4 inch tie rod must connect both bases of each longitudinal side.

This engineering study reviews and evaluates all available methods for transportation of 500-mL grab sample bottles, reviews and evaluates transportation requirements and schedules and analyzes and recommends the most cost-effective method for transporting 500-mL grab sample bottles.

This Engineering Study was to evaluate the current equipment and operating procedures to determine if changes could be made to improve ALARA and evaluate the feasibility of implementing the proposed solutions. As part of this study input from the cognizant characterization engineers and operating sampling crews was obtained and evaluated for ALARA improvements.

Atom-by-atom and concerted hopping of ad-dimers on the open (100) surface of fcc metals are studied by means of density-functional calculations. The adatom interaction is relatively short-ranged, and beyond next-nearest neighbors ad-dimers are effectively dissociated. Diffusion takes place by a simple shearing process, favored because it maximizes adatom coordination at the transition state This holds for Al, Au, and Rh, and is likely a general result because geometrical arguments dominate over details of the electronic structure.

This document presents the results of a hazard identification and evaluation performed on the 244-AR Vault Facility to close a USQ (USQ No.TF-98-0785, Potential Inadequacy in Authorization Basis (PIAB): To Evaluate Miscellaneous Facilities Listed In HNF-2503 And Not Addressed In The TWRS Authorization Basis) that was generated as part of an evaluation of inactive TWRS facilities. A hazard evaluation for the Hanford Site 244-AR Vault Facility was performed. The process and results of the hazard evaluation are provided in this document. A previous hazard evaluation was performed for the 244-AR Vault Facility in 1996 in support of the Basis for Interim Operation (BIO) (HNF-SD-WM-BIO-001, 1998, Revision 1) of the Tank Waste Remediation System (TWRS). The results of that evaluation are provided in the BIO. Upon review of those results it was determined that hazardous conditions that could lead to the release of radiological and toxicological material from the 244-AR vaults due to flooding was not addressed in the original hazards evaluation. This supplemental hazard evaluation addresses this oversight of the original hazard evaluation. The results of the hazard evaluation were compared to the current TWRS BIO to identify any hazardous conditions where Authorization Basis (AB) controls may not be sufficient …

Exclusive and semi-exclusive processes, the diffractive dissociation of hadrons into jets, and hard diffractive processes such as vector meson leptoproduction provide new testing grounds for QCD and essential information on the structure of light-cone wavefunctions of hadrons, particularly the pion distribution amplitude. I review the basic features of the leading-twist QCD predictions and the problems and challenges of studying QCD at the amplitude level. The application of the light-cone formalism to the exclusive semi-leptonic decay of heavy hadrons is also discussed.

Exclusive and semi-exclusive processes, the diffractive dissociation of hadrons into jets, and hard diffractive processes such as vector meson leptoproduction provide new testing grounds for QCD and essential information on the structure of light-cone wavefunctions of hadrons, particularly the pion distribution amplitude. I review the basic features of the leading-twist QCD predictions and the problems and challenges of studying QCD at the amplitude level. The application of the light-cone formalism to the exclusive semi-leptonic decay of heavy hadrons is also discussed.

Alteration may be expected for spent nuclear fuel exposed to groundwater under oxidizing conditions such as that which exist at the proposed nuclear waste repository at Yucca Mountain, Nevada. The actinide elements released during the corrosion of spent fuel may be incorporated into the structures of secondary U{sup 6+} phases. The incorporation of transuranics into the crystal structures of the alteration products may significantly decrease their mobility. A series of precipitation tests were conducted at 90 C to determine the potential incorporation of Ce{sup 4+} and Nd{sup 3+} (surrogates for Pu{sup 4+} and Am{sup 3+}, respectively) into uranyl phase. Dehydrated schoepite (UO{sub 3}{center_dot}0.8-1.0HP{sub 2}O) was produced by hydrolysis of a uranium oxyacetate solution containing either cerium or neodymium. ICP-MS analysis of the leachant, leachate, and solid phase reaction products which were dissolved in a HNO{sub 3} solution indicates that 26 ppm of Ce was incorporated into dehydrated schoepite. ICP-MS results from the Nd-doped tests indicate significant neodymium incorporation as well, however, the heterogeneous distribution of Nd in the solid phase noted during the AEM/EELS examination implies that neodymium may not incorporate into the structure of dehydrated schoepite.

This functions and requirements document defines the baseline requirements and criteria for the design, purchase, fabrication, construction, installation, and operation of automated liquid level gauge instruments in the Tank Farms. This document is intended to become the technical baseline for current and future installation, operation and maintenance of automated liquid level gauges in single-shell and double-shell tank farms.

A Waste Sluicing System (WSS) is scheduled for installation in nd waste storage tank 241-C-106 (106-C). The WSS will transfer high rating sludge from single shell tank 106-C to double shell waste tank 241-AY-102 (102-AY). Prior to installation of the WSS, a heel pump and a transfer pump will be removed from tank 106-C and an agitator pump will be removed from tank 102-AY. Special flexible receivers will be used to contain the pumps during removal from the tanks. After equipment removal, the flexible receivers will be placed in separate containers (packagings). The packaging and contents (packages) will be transferred from the Tank Farms to the Central Waste Complex (CWC) for interim storage and then to T Plant for evaluation and processing for final disposition. Two sizes of packagings will be provided for transferring the equipment from the Tank Farms to the interim storage facility. The packagings will be designated as the WSSP-1 and WSSP-2 packagings throughout the remainder of this Safety Evaluation for Packaging (SEP). The WSSP-1 packagings will transport the heel and transfer pumps from 106-C and the WSSP-2 packaging will transport the agitator pump from 102-AY. The WSSP-1 and WSSP-2 packagings are similar except for the length.

Fluid Catalytic Cracking (FCC) technology is the most important process used by the refinery industry to convert crude oil to valuable lighter products such as gasoline. Process development is generally very time consuming especially when a small pilot unit is being scaled-up to a large commercial unit because of the lack of information to aide in the design of scaled-up units. Such information can now be obtained by analysis based on the pilot scale measurements and computer simulation that includes controlling physics of the FCC system. A Computational fluid dynamic (CFD) code, ICRKFLO, has been developed at Argonne National Laboratory (ANL) and has been successfully applied to the simulation of catalytic petroleum cracking risers. It employs hybrid hydrodynamic-chemical kinetic coupling techniques, enabling the analysis of an FCC unit with complex chemical reaction sets containing tens or hundreds of subspecies. The code has been continuously validated based on pilot-scale experimental data. It is now being used to investigate the effects of scaled-up FCC units. Among FCC operating conditions, the feed injection conditions are found to have a strong impact on the product yields of scaled-up FCC units. The feed injection conditions appear to affect flow and heat transfer patterns and the …

Fluid Catalytic Cracking (FCC) technology is the most important process used by the refinery industry to convert crude oil to valuable lighter products such as gasoline. New and modified processes are constantly developed by refinery companies to improve their global competitiveness and meet more stringent environmental regulations. Short residence time FCC riser reactor is one of the advanced processes that the refining industry is actively pursuing because it can improve the yield selectivity and efficiency of an FCC unit. However, as the residence time becomes shorter, the impact of the mixing between catalyst and feed oil at the feed injection region on the product yield becomes more significant. Currently, most FCC computer models used by the refineries perform sophisticated kinetic calculations on simplified flow field and can not be used to evaluate the impact of fluid mixing on the performance of an FCC unit. Argonne National Laboratory (AFL) is developing a computational fluid dynamic (CFD) code ICRKFLO for FCC riser flow modeling. The code, employing hybrid hydrodynamic-chemical kinetic coupling techniques, is used to investigate the effect of operating and design conditions on the product yields of FCC riser reactors. Numerical calculations were made using the code to examine the impacts …

This project is concerned with the development of a coal database providing information to the public and private research sectors on 30 coal samples. The information from these samples, along with information previously collected on 26 samples, will be distributed to DOE contractors performing coal research.

This engineering study looks at the solids/liquids separation unit operations after the acid dissolution of the K Basin sludge treatment. Unit operations considered were centrifugation, filtration (cartridge, cross flow, and high shear filtration) and gravity settling. The recommended unit operations for the solids/liquids separations are based upon the efficiency, complexity, and off-the-shelf availability and adaptability. The unit operations recommended were a Robatel DPC 900 centrifuge followed by a nuclearized 31WM cartridge filter. The Robatel DPC 900 has been successfully employed in the nuclear industry on a world wide scale. The 31WM cartridge filter has been employed for filtration campaigns in both the government and civilian nuclear arenas.

This engineering study evaluates the use of physical separation technologies to separate organic ion exchange resin from KE Basin sludge prior to nitric acid dissolution. This separation is necessitate to prevent nitration of the organics in the acid dissolver. The technologies under consideration are: screening, sedimentation, elutriation. The recommended approach is to first screen the Sludge and resin 300 microns then subject the 300 microns plus material to elutriation.