Using a diamond-anvil cell (DAC) phase transformation and room temperature Equation of State (EOS) for some actinides and lanthanides were studied to multimegabar (megabar = 100 GPa) pressures. Experimental data are compared with the theoretically predicted crystal structural changes and the pressure-volume relationships. There is a general agreement between theory and experiment for the structural changes in the lighter actinides, however in detail there are some discrepancies still. A generalized trend for the phase transformations in the lanthanides can be seen, which again has broad agreement with theory. We conclude that an accurate and robust theoretical base for predicting the phase transformations in the f-electron metals can be developed by incorporating the DAC data.

This document outlines the hazard classification methodology used to determine the hazard classification of the NIF LTAB, OAB, and the support facilities on the basis of radionuclides and chemicals. The hazard classification determines the safety analysis requirements for a facility.

Automatic control of fine coal cleaning circuits has traditionally been limited by the lack of sensors for on-line ash analysis. Although several nuclear-based analyzers are available, none have seen widespread acceptance. This is largely due to the fact that nuclear sensors are expensive and tend to be influenced by changes in seam type and pyrite content. Recently, researchers at VPI&SU have developed an optical sensor for phosphate analysis. The sensor uses image processing technology to analyze video images of phosphate ore. It is currently being used by PCS Phosphate for off-line analysis of dry flotation concentrate. The primary advantages of optical sensors over nuclear sensors are that they are significantly cheaper, are not subject to measurement variations due to changes in high atomic number minerals, are inherently safer and require no special radiation permitting. The purpose of this work is to apply the knowledge gained in the development of an optical phosphate analyzer to the development of an on-line ash analyzer for fine coal slurries. During the past quarter, an industrially-hardened version of the video-based ash analyzer was designed and constructed. All components are now in place at the Middle Fork plant site awaiting the installation of a sample line …

This report contains tables of the analytical results from grab samples from tank 241-AY-101. Activity levels of radionuclides are tabulated. This tanks has not been watch listed.

The goal of this research is to engineer enzymes to be efficient and economically attractive catalysts for the chemical industry. The author is attempted to demonstrate generally-applicable approaches to enzyme improvement as well as develop specific catalysts for potential industrial application. The paper describes the progress in two projects: (a) Random mutagenesis of pNB esterase: Improved activity and stability; and (2) Subtilisin mutants exhibiting improved ligase activity in organic solvents.

Two auger samples from tank 241-C-204 (C-204) were submitted to the 222-S Laboratories for safety screening analyses, consisting of differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), and total alpha activity. Sampling and analysis requirements are presented in the Sampling and Analysis Plan (SAP) (which was adapted with minimal changes from the original Tank Characterization Plan. The Tank Characterization Plan was subsequently revised, and the sampling and analytical requirements were inadvertently deleted). The DSC results for all samples from the tank exceeded the action limit of 481 J/g. Secondary analyses [total organic carbon (TOC) and adiabatic calorimetry], as negotiated with the safety program, were performed. The TOC results also exceeded the action limit of 3 weight percent. However, the moisture content of the samples is between 50 and 60%, and the results of adiabatic calorimetry testing indicated that the sample material would not support a propagating exothermic reaction. Primary and secondary analytical results were reported previously. The 90-day report indicated that additional heat capacity and DSC tests would be performed to further interpret the adiabatic calorimetry results. However, the laboratory has not been able to successfully perform heat capacity tests at this time. Therefore, this report is being issued without these …

The authors present direct measurements of the Z{sup 0}-lepton coupling asymmetries, A{sub e}, A{sub {mu}}, and A{sub {tau}}. It is based on a data sample selected from 170 k Z{sup 0} decays collected by the SLD detector. The Z`s are produced by collisions of polarized e{sup {minus}} with unpolarized e{sup +} bunches at SLC. The couplings are extracted from the measurement of the left-right forward-backward asymmetry for each lepton species. The preliminary results (using information from all leptonic data for A{sub e}) are: A{sub e} = 0.148 {+-} 0.016, A{sub {mu}} = 0.102 {+-} 0.033 and A{sub {tau}} = 0.190 {+-} 0.034.

The concentrations of mercury at the FAVC inlet and exit were measured during the BL1 and PX6 runs of the Integrated DWPF Melter System (IDMS) with the HEME bypassed and without the ammonia scrubber. The results showed that mercury concentrations of approximately 1.02-12.7 (mean 5.74) times saturation occurred at the FAVC exit. The concentration of mercury at the FAVC inlet was found to be 0.66-6.2 times the saturation value (based on the SRAT condenser exit). In the PX7 run, the ammonia scrubber was used and the FAVC HEME was not bypassed. The results from this run showed that the FAVC inlet concentrations again were above saturation (1.45-15.5 times saturation), but that the FAVC exit concentrations were only 0.02-0.41 times saturation (except for one data point at 1.61 times saturation). Operation of the FAVC without the HEME could therefore result in FAVC exit mercury concentrations of greater than 5.74 times saturation, which would result in DWPF emitting greater than 405 lb/yr of mercury at 100 percent attainment; this quantity is well in excess of the permit limit of 175 lb/yr (for all of DWPF). However, with the HEME in place, the emissions are predicted to be only about 40 lb/yr for …

The purpose of this Documentation and Analysis for Packaging (DAP) is to certify that the packaging system currently in use for the 100 B and C Area large scale excavation and remediation campaign, meets the intent of U.S. Department of Transportation(DOT) requirements for bulk packaging (49 CFR 173.427) of radioactive materials, up to and including low specific activity (LSA) I quantities of Class 7 material.

This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-B-204. This report supports the requirements of Tri-Party Agreement Milestone M-44-09.

The Equipment Qualification Test described in this test procedure document is the acceptance test procedure (ATP) for the LDUA Baseline System. It verifies that the equipment is complete and in working order, and demonstrates its readiness for being deployed into an actual underground storage tank.

A side view of the double sided ladder is shown in Figure 1. There are two types of double sided ladder; 6 chip and 9 chip. The 6 chip ladder has three SVX II chips mounted directly opposite the cooling channel and 3 chips mounted at the ladder end. The 9 chip ladder has 4 SVX II chips directly opposite the cooling channel and 5 chips at the ladder end. The power density is highest in the 6 chip ladder. All plots and calculations in this Engineering Note pertain to the 6 chip ladder with the understanding that the 9 chip temperature profile is somewhat improved over the 6 chip due to the reduced power density in the row of chips opposite the cooling channel. The two dimensional finite difference technique used for these calculations is described in DOEN 447 and will not be described here. The assumed thermal conductivity of beryllium is 190 W/m-K, and that of silicon is 149 W/m-K. The SVX II power dissipation is assumed 0.400 W. There is no cable or hybrid component power dissipation in this set of simulations. The epoxy in the glue joints consists of 2 mils thickness of thermally conductive epoxy …