This report discusses the Background, Issues, and Options for Congress on Defense Procurement. The full funding policy is a federal budgeting rule imposed on DOD by Congress in the 1950s that requires the entire procurement cost of a weapon of military equipment.

OAK-B135 This paper is submitted in fulfillment of DOE Grant No. DE-FG03-015F22369 on the experience of western states/provinces with demand response (DR) in the electricity sector. Demand-side resources are often overlooked as a viable option for meeting load growth and addressing the challenges posed by the region's aging transmission system. Western states should work together with utilities and grid operators to facilitate the further deployment of DR programs which can provide benefits in the form of decreased grid congestion, improved system reliability, market efficiency, price stabilization, hedging against volatile fuel prices and reduced environmental impacts of energy production. This report describes the various types of DR programs; provides a survey of DR programs currently in place in the West; considers the benefits, drawbacks and barriers to DR; and presents lessons learned and recommendations for states/provinces.

As was reported in our previous work, accurate, nondisturbing near-anode measurements of the plasma density, electron temperature, and plasma potential performed with biased and emissive probes allowed the first experimental identification of both electron-repelling (negative anode fall) and electron-attracting (positive anode fall) anode sheaths in Hall thrusters. An interesting new phenomenon revealed by the probe measurements is that the anode fall changes from positive to negative upon removal of the dielectric coating, which appears on the anode surface during the course of Hall thruster operation. As reported in the present work, energy dispersion spectroscopy analysis of the chemical composition of the anode dielectric coating indicates that the coating layer consists essentially of an oxide of the anode material (stainless steel). However, it is still unclear how oxygen gets into the thruster channel. Most importantly, possible mechanisms of anode fall formation in a Hall thruster with a clean and a coated anodes are analyzed in this work; practical implication of understanding the general structure of the electron-attracting anode sheath in the case of a coated anode is also discussed.

The River Protection Project-Waste Treatment Plant (RPP-WTP) requested Savannah River National Laboratory (SRNL) to conduct small-scale foaming and antifoam testing using actual Hanford waste and simulants subjected to air sparging. The foaminess of Hanford tank waste solutions was previously demonstrated in SRNL during WTP evaporator foaming and ultrafiltration studies and commercial antifoam DOW Q2-3183A was recommended to mitigate the foam in the evaporators. Currently, WTP is planning to use air spargers in the HLW Lag Storage Vessels, HLW Concentrate Receipt Vessel, and the Ultrafiltration Vessels to assist the performance of the Jet Pulse Mixers (JPM). Sparging of air into WTP tanks will induce a foam layer within the process vessels. The air dispersion in the waste slurries and generated foams could present problems during plant operation. Foam in the tanks could also adversely impact hydrogen removal and mitigation. Antifoam (DOW Q2-3183A) will be used to control foaming in Hanford sparged waste processing tanks. These tanks will be mixed by a combination of pulse-jet mixers and air spargers. The percent allowable foaminess or freeboard in WTP tanks are shown in tables.

In support of Low-Curie Salt (LCS) process validation at the Savannah River Site (SRS), Liquid Waste Disposition (LWD) has undertaken a program of tank characterization, including salt sampling. As part of this initiative, they sampled the surface and subsurface of Tank 10H saltcake using a series of three 12-inch long sample tubes. These tubes each contain 1-foot long segments of the saltcake from one location, representing the top three feet of saltcake. The primary objective of the characterization that will be useful to the selection and processing of the next waste tanks. Most important is the determination of the Cs-137 concentration and liquid retention properties of Tank 10H saltcake to confirm acceptability of processing. Additional chemical analyses are performed to provide information on salt elemental, ionic, and radiological composition to aid in assessment of the suitability of processing drained and dissolved material and in refining the information in the waste characterization system (WCS).

This report provides the final results of analyses of the saltcake core sample and a separate supernate sample from Tank 29H. The supernate sample was markedly different from the drained interstitial liquid. The Tank 29H supernate had a reduction in 238Pu upon filtering through a 0.45-micron filter. Approximately 25 per cent of the U is in suspension in the supernate and can be removed by filtration. As expected, the radionuclides Cs-137 and Tc-99 are entirely soluble and the actinides are largely insoluble, in the interstitial liquid, within experimental error. It is not known how representative this saltcake sample is for the entire tank. There is considerably more liquid present in this sample than in most other tank samples examined thus far. The history of the tank indicates that some of the saltcake in the top layer likely dissolved by the addition of low ionic strength solutions over the past few years. Also, the sample was collected at the bottom of a 7-foot well that was mined into the saltcake with water. These water additions could have dissolved the sodium nitrate in the top layer, and left behind a layer containing the remaining salts, including those of aluminum, although it is …

The aim of the proposed research is to use electroactive ion exchange materials to remove anionic contaminants from HLW wastes and process streams. An ion exchange process using electroactive materials sorbs contaminants selectively and then expels (elutes) them electrochemically by changing the charge balance through redox reactions in the sorbent as opposed to requiring the addition of a chemical eluent. Such processes can theoretically remove anions (e.g., pertechnetate, chromate, and perchorate) and concentrate them in a separate product stream while adding no process chemicals. A practical implementation in HLW process facilities would be a breakthrough in the ability of DOE to economically minimize waste and prevent pollution throughout the complex. To enable this, our work focuses on manipulating specific properties of redox polymers to control the hydrophobicity and ion-pair properties pertinent to the reversibility, selectivity, stability, intercalation/de-intercalation rates, and capacity of the polymers.

The U.S. Department of Energy (DOE) has selected Uranium Disposition Services, LLC (UDS) to proceed with disposition of the inventory of depleted uranium hexafluoride (DUF{sub 6}) for which DOE has management responsibility. To accomplish this task, UDS will construct and operate facilities at two DOE-owned sites, one near Paducah, Kentucky, and another near Portsmouth, Ohio, to convert DUF{sub 6} to uranium oxide (principally U{sub 3}O{sub 8}). The off-gas treatment system for the conversion process will produce aqueous hydrogen fluoride (AqHF), also known as hydrofluoric acid, and a relatively small amount of calcium fluoride (CaF{sub 2}), each containing some residual radioactive material. As part of its contractual charge, UDS must identify and implement a disposition for all three products generated by the DUF{sub 6} conversion facilities: uranium oxide, AqHF, and CaF{sub 2}. The UDS DUF{sub 6} Conversion Product Management Plan (DUF{sub 6}-UDS-PLN-004, September 2003) concludes that a viable commercial market exists for AqHF, which, if not sold, would have to be neutralized, producing a relatively large quantity of additional CaF{sub 2}. Although CaF{sub 2} has very limited market potential, there is some possibility that it also could be sold. If these potential markets could be developed, DOE would save the costs …

One of the throughput limitations for the Actinide Removal Process (ARP) and Salt Waste Processing Facility is the lengthy sorption time of plutonium on monosodium titanate(MST). Argonne National Laboratory (ANL) personnel proposed use of the In-Situ-Mixed Iron Oxide (IS-MIO) process, which removes strontium and actinides from waste streams with faster reaction kinetics than the MST process. The Savannah River National Laboratory and ANL received funding to develop the IS-MIO process for deployment at the Savannah River Site. Personnel performed simulant filtration tests to evaluate the process. They prepared 100 L of simulated SRS high level waste, added IS-MIO solutions to the simulated waste, mixed the solutions for four hours, and filtered the slurry in a bench-scale crossflow filter. The simulant was designed to maximize strontium solubility; it was not designed to match a particular tank composition. The crossflow filter was 3/8 inch internal diameter, 2 feet long, and possessing a 0.196 ft2 internal surface area. Researchers also performed a series of decontamination tests using actual waste. They prepared a multi-tank composite adjusted it to 5.6 M sodium, and allowed it to equilibrate. They used this material in six tests. Four of the tests used IS-MIO solutions, one of the tests …

This report is written in response to commonly asked questions about military funeral honors. It provides information on the eligibility criteria, required components of the honor detail, and the funeral ceremony. It also cites legislation that mandates that the Department of Defense (DOD) make military funeral honors available to every eligible veteran upon request.

This report contains the federal pension and retirement benefits of the former presidents.

None

None

This report discusses the radio frequency spectrum that is used for all forms of wireless communications, including cellular telephony, paging, personal communications service, radio and television broadcast, telephone radio relay, aeronautical and maritime radio navigation, and satellite command and control.

This report gives an overview of Indonesian elections in 2004.

EOS7C is a TOUGH2 module for multicomponent gas mixtures in the systems methane carbon dioxide (CH4-CO2) or methane-nitrogen (CH4-N2) with or without an aqueous phase and H2O vapor. EOS7C uses a cubic equation of state and an accurate solubility formulation along with a multiphase Darcy s Law to model flow and transport of gas and aqueous phase mixtures over a wide range of pressures and temperatures appropriate to subsurface geologic carbon sequestration sites and natural gas reservoirs. EOS7C models supercritical CO2 and subcritical CO2 as a non-condensible gas, hence EOS7C does not model the transition to liquid or solid CO2 conditions. The components modeled in EOS7C are water, brine, non-condensible gas, gas tracer, methane, and optional heat. The non-condensible gas (NCG) can be selected by the user to be CO2 or N2. The real gas properties module has options for Peng-Robinson, Redlich-Kwong, or Soave-Redlich-Kwong equations of state to calculate gas mixture density, enthalpy departure, and viscosity. Partitioning of the NCG and CH4 between the aqueous and gas phases is calculated using a very accurate chemical equilibrium approach. Transport of the gaseous and dissolved components is by advection and Fickian molecular diffusion. We present instructions for use and example problems to …

Radionuclide contamination in the soil and groundwater at U.S. Department of Energy (DOE) sites is a severe problem that requires monitoring and remediation. Radionuclide measurement techniques are needed to monitor surface waters, groundwater, and process waters. Typically, water samples are collected and transported to an analytical laboratory, where costly radiochemical analyses are performed. To date, there has been very little development of selective radionuclide sensors for alpha- and beta-emitting radionuclides such as 90Sr, 99Tc, and various actinides of interest. The objective of this project is to investigate novel sensor concepts and materials for sensitive and selective determination of beta- and alpha-emitting radionuclide contaminants in water. To meet the requirements for low-level, isotope-specific detection, the proposed sensors are based on radiometric detection. As a means to address the fundamental challenge of the short ranges of beta and alpha particle s in water, our overall approach is based on localization of preconcentration/separation chemistries directly on or within the active area of a radioactivity detector. Automated microfluidics is used for sample manipulation and sensor regeneration or renewal. The outcome of these investigations will be the knowledge necessary to choose appropriate chemistries for selective preconcentration of radionuclides from environmental samples, new materials that combine …

A new multigrid algorithm based on the method of self-correction for the solution of elliptic problems is described. The method exploits information contained in the residual to dynamically modify the source term (right-hand side) of the elliptic problem. It is shown that the self-correcting solver is more efficient at damping the short wavelength modes of the algebraic error than its standard equivalent. When used in conjunction with a multigrid method, the resulting solver displays an improved convergence rate with no additional computational work.

None

None

None