Engineering topics
Publications and source records attributed to Lee, Hope.
We report the coupling of tin-vacancy centers (SnV-) to 1D photonic crystal cavities in diamond thin-films; we observe a quality factor of ~6000 and a 10-fold PL enhancement.
We couple tin-vacancy (SnV-) centers in thin-film diamond to one-dimensional photonic crystal cavities of different orientations and develop a spontaneous emission model that rigorously quantifies Purcell factors and the branching ratio of the zero-phonon line (ZPL) transitions.
The negatively charged tin-vacancy center in diamond (SnV − ) is an emerging platform for building the next generation of long-distance quantum networks. This is due to the SnV − ’s favorable optical and spin properties including bright emission, insensitivity to electronic noise, and long spin coherence times at temperatures above 1 K. Here, we demonstrate measurement of a single SnV − electronic spin with a single-shot readout fidelity of 87.4%, which can be further improved to 98.5% by conditioning on multiple readouts. In the process, we develop understanding of the relationship between strain, magnetic field, spin readout, and microwave spin control. We show that high-fidelity readout is compatible with rapid microwave spin control, demonstrating a favorable parameter regime for use of the SnV − center as a high-quality spin-photon interface. Finally, we use weak quantum measurement to study measurement-induced dephasing; this illuminates the fundamental interplay between measurement and decoherence in quantum mechanics, and provides a universal method to characterize the efficiency of color-center spin readout. Taken together, these results overcome an important hurdle in the development of the SnV − -based quantum technologies and, in the process, develop techniques and understanding broadly applicable to the study of solid-state quantum emitters.
Isotopes of iodine were generated during plutonium production within the nine production reactors at the U.S. Department of Energy Hanford Site. The short half-life 131I that was released from the fuel into the atmosphere during the dissolution process (when the fuel was dissolved) in the Hanford Site 200 Area is no longer present at concentrations of concern in the environment. The long half-life 129I generated at the Hanford Site during reactor operations was (1) stored in single-shell and double-shell tanks, (2) discharged to liquid disposal sites (e.g., cribs and trenches), (3) released to the atmosphere during fuel reprocessing operations, or (4) captured by off-gas absorbent devices (silver reactors) at chemical separations plants (PUREX, B-Plant, T-Plant, and REDOX). Releases of 129I to the subsurface have resulted in several large, though dilute, plumes in the groundwater. There is also 129I remaining in the vadose zone beneath disposal or leak locations. The fate and transport of 129I in the environment and potential remediation technologies are currently being studied as part of environmental remediation activities at the Hanford Site. A conceptual model describing the nature and extent of subsurface contamination, factors that control plume behavior, and factors relevant to potential remediation processes is needed to support environmental remedy decisions. Because 129I is an uncommon contaminant, relevant remediation experience and scientific literature are limited. In addition, its behavior in subsurface is different from that of other more common and important contaminants (e.g., U, Cr and Tc) in terms of sorption (adsorption and precipitation), and aqueous phase species transformation via redox reactions. Thus, the conceptual model also needs to both describe known contaminant and biogeochemical process information and identify aspects about which additional information is needed to effectively support remedy decisions.
In 1943, construction began on the first of nine nuclear reactors at the Hanford Site to produce plutonium for the development of atomic weapons for the Manhattan Project during World War II and throughout the Cold War. Over a production period lasting from 1944 to 1987, approximately 110,000 tons of nuclear fuel was processed. During the production period, billions of gallons of liquid nuclear waste and millions of tons of solid waste were produced. Approximately 4.7 Ci of radioiodine (I-129) was discharged to liquid disposal sites, during disposition of the waste. Following percolation of the liquid waste through the vadose zone, three large I-129 groundwater plumes have formed beneath Central Plateau Facilities including both 200 East and 200 West Areas. Analysis of I-129 plumes in the 200-ZP-1 Operable Unit (OU) (200 West Area) showed iodine speciation that was dominated by iodate even though iodide was thought to be dominant species in waste. Experimental results demonstrated that iodate interacts with calcite via a co-precipitation and/or adsorption mechanism. From sorption experiments performed on Hanford sediments, iodate interacted more strongly than iodide during adsorption experiments. These results would indicate that iodate migration would be retarded compared to iodide, but results from groundwater samples obtained from eight wells in the 200 ZP-1 OU did not support this hypothesis. Due to different chemical processes used during plutonium processing, iodine species in other plumes such as in the 200-UP-1 OU (200 West Area) may be different. In addition, species distribution may change longitudinally between the source area and the distal end of the plume. Groundwater samples will be taken at a location near the source, in the middle of the plume and at the distal end of the plume. These samples will be analyzed for iodine speciation using ion chromatography coupled to an inductively coupled plasma mass spectrometer. Results from the different samples will be compared to give an initial determination of species distribution at different locations along the plume. Data generated from these samples can then be used to inform the conceptual model that is being developed for iodine as part of an evaluation of remediation options for the 200-UP-1 OU. (authors)
In June of 2012 the CH2M Hill Plateau Remediation Company completed construction of a 2,500 gallon-per-minute (gpm) pump and treat (P and T) system designed to remove technetium-99, uranium, carbon tetrachloride, trichloroethene, nitrate, and total and hexavalent chromium from incoming groundwater. The entire pump and treat system consists of the following primary components: 1) extraction wells (20+); 2) a radionuclide removal facility; 3) a biological system; 4) sludge processing; 5) vapor processing; and 6) injection wells. Overall efficiency of the 200 West P and T has been adversely impacted due to fouling in vertical injection wells where treated water is being reinjected into the subsurface. Fouling of the wells is thought to be caused by bacteria producing extracellular polymeric substances (EPS), as well as high manganese and iron in the biofilm. Due to decreased specific injectivity, all injection wells are on a maintenance schedule requiring rehabilitation. During rehabilitation, the wells are out of service affecting the overall capacity of the P and T, plus the rehabilitation process adds hundreds of thousands of dollars of cost to operate the P and T each year. Chemical and biological foulants may be coming from the P and T or are already present in the subsurface and active pumping has stimulated growth of the microbes present. Chemical and microbiological characterization efforts are in progress for the biological plant and injection well system to determine causative agents in the biofouling. P and T effluent tank samples, injection well distribution tanks, bailed samples from the fouled well, and post-rehabilitation samples were analyzed. Chemical constituents analyzed include, sulfate, phosphorus, chemical oxygen demand, total organic carbon, and iron. Microbial characterization included total heterotrophs, anaerobic heterotrophs, nitrate reducing bacteria, iron reducing bacteria and sulfate reducing bacteria. Molecular biological tools employed included 16S rRNA meta-genomes, and functional gene analysis using qPCR. Chemical analysis of the P and T effluent and injection well tanks showed the presence of ∼6.5 mg/L nitrate, 96 mg/L sulfate and phosphorus levels below 1 mg/L. Bailed samples from the injection well showed similar concentrations for each chemical, but following cleaning, TOC, total iron, manganese and other constituents were higher than prior to cleaning. These data show that bacterial nutrients and metals that may precipitate are present in the well water and are likely the causative agent in the biofouling. (authors)
Technetium management is a high-priority activity for the U.S. Department of Energy (DOE) Office of Environmental Management (EM) complex. Waste management and remediation issues involving technetium represent environmental risks and challenges that are unique to DOE. This plan lays out the technology development activities that are underway as well as future technology needs to address technetium issues across DOE EM sites and across programmatic areas of tank waste, groundwater and soils, and facility decommissioning and deactivation in order to be comprehensive and to allow integration of similar activities. The program was developed in close coordination with site representatives and program offices. Activities and needs that were identified share common themes and were grouped into areas of characterization, treatment, and disposition. Characterization includes understanding the inventory at particular locations, the chemical species, and chemical and physical behavior, whether in a treatment process flowsheet or a geological setting that displays periodic contaminant releases. The tools for characterization in these different environments might use the same sensors or protocols. Treatment options include methods to capture technetium such as ion-exchange or manipulation of oxidation states, which also may be applied across program areas. Disposition includes end-points of the processes and environmental risk, including waste form behavior, mobility of technetium once it is treated or remediated, and long-term monitoring. Disposition represents integration of all cleanup actions at a site. (authors)