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DOE OSTI2014

Campbell Creek Research Homes: FY2013 Annual Performance Report (October 1, 2012–September 30, 2013)

The Campbell Creek project is funded and managed by the Tennessee Valley Authority (TVA) Technology Innovation, Energy Efficiency, Power Delivery, and Utilization Office. Technical support is provided under contract by Oak Ridge National Laboratory (ORNL) and the Electric Power Research Institute (EPRI). The project was designed to determine the relative energy efficiency of typical new home construction, of retrofitting of existing homes, and of high-performance new homes built from the ground up for energy efficiency.

Annual Report↗
DOE OSTI2014

Letter Report Documenting Progress of Second Generation ATF FeCrAl Alloy Fabrication

Development of the 2 nd generation ATF FeCrAl alloy has been initiated, and a candidate alloy was selected for trial tube fabrication through hot-extrusion and gun-drilling processes. Four alloys based on Fe-13Cr-4.5Al-0.15Y in weight percent were newly cast with minor alloying additions of Mo, Si, Nb, and C to promote solid-solution and second-phase precipitate strengthening. The alloy compositions were selected with guidance from computational thermodynamic tools. The lab-scale heats of ~ 600g were arc-melted and drop-cast, homogenized, hot-forged and -rolled, and then annealed producing plate shape samples. An alloy with Mo and Nb additions (C35MN) processed at 800°C exhibits very fine sub-grain structure with the sub-grain size of 1-3μm which exhibited more than 25% better yield and tensile strengths together with decent ductility compared to the other FeCrAl alloys at room temperature. It was found that the Nb addition was key to improving thermal stability of the fine sub-grain structure. Optimally, grains of less than 30 microns are desired, with grains up to and order of magnitude in desired produced through Nb addition. Scale-up effort of the C35MN alloy was made in collaboration with a commercial cast company who has a capability of vacuum induction melting. A 39lb columnar ingot with ~81mm diameter and ~305mm height (with hot-top) was commercially cast, homogenized, hot-extruded, and annealed providing 10mm-diameter bar-shape samples with the fine sub-grain structure. This commercial heat proved consistent with materials produced at ORNL at the lab-scale. Tubes and end caps were machined from the bar sample and provided to another work package for the ATF-1 irradiation campaign in the milestone M3FT-14OR0202251.

2nd generation ATF FeCrAl alloy↗
DOE OSTI2014

MCNP(TM) Release 6.1.1 beta: Creating and Testing the Code Distribution

This report documents the preparations for and testing of the production release of MCNP6™1.1 beta through RSICC at ORNL. It addresses tests on supported operating systems (Linux, MacOSX, Windows) with the supported compilers (Intel, Portland Group and gfortran). Verification and Validation test results are documented elsewhere. This report does not address in detail the overall packaging of the distribution. Specifically, it does not address the nuclear and atomic data collection, the other included software packages (MCNP5, MCNPX and MCNP6) and the collection of reference documents.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2013

Processing of Sintered Mo Disks Using Hydrogen Peroxide

Dissolution studies performed on NorthStar and ORNL disks show that an increase in sintering temperature has a negative effect on dissolution rates in 30% hydrogen peroxide. This is due to changes in the microstructure of sintered Mo powder. At higher sintering temperatures, the powder particles coalesce, form diffusion bonds, and grow into larger grains, which reduce the open porosity of the disks. The remaining porosity becomes trapped within the grains, and therefore the dissolution rates are very low. We also observed that different starting materials lead to different dissolution properties, and in some cases, even high sintering temperature at 1600°C does not produce disks with high packing densities. Studies with NorthStar disks showed that increased packing density can be achieved by increased pressing conditions without affecting the dissolution rates if mild sintering conditions are used. Future experiments will focus on producing sintered Mo disks produced from recovered Mo material and on optimizing the sintering process to produce disks with >90% packing density and good dissolution rates.

Dissolution↗
DOE OSTI2012

Generation of Collapsed Cross Sections for Hatch 1 Cycles 1-3 and Generation of Generic BWR Reflector Cross Sections

Under NRC-JCN-V6361, Oak Ridge National Laboratory (ORNL) was tasked to develop and run SCALE/TRITON models for generation of collapsed few-group cross sections and to convert the cross sections to PMAXS format using the GENPMAXS conversion utility for use in PARCS/PATHS simulations of Hatch Unit 1, cycles 1-3. This letter report documents the final models used to produce the Hatch collapsed cross sections.

Ade, Brian J.↗
DOE OSTI2013

Conceptual Design Parameters for HFIR LEU U-Mo Fuel Conversion Experimental Irradiations

The High Flux Isotope Reactor (HFIR) is a versatile research reactor that is operated at the Oak Ridge National Laboratory (ORNL). The HFIR core is loaded with high-enriched uranium (HEU) and operates at a power level of 85 MW. The primary scientific missions of the HFIR include cold and thermal neutron scattering, materials irradiation, and isotope production. An engineering design study of the conversion of the HFIR from HEU to low-enriched uranium (LEU) fuel is ongoing at the Oak Ridge National Laboratory. The LEU fuel considered is based on a uranium-molybdenum alloy that is 10 percent by weight molybdenum (U-10Mo) with a 235 U enrichment of 19.75 wt %. The LEU core design discussed in this report is based on the design documented in ORNL/TM-2010/318. Much of the data reported in Sections 1 and 2 of this document was derived from or taken directly out of ORNL/TM-2010/318. The purpose of this report is to document the design parameters for and the anticipated normal operating conditions of the conceptual HFIR LEU fuel to aid in developing requirements for HFIR irradiation experiments.

Chandler, David↗
DOE OSTI2013

Traction Drive and Gearing Design Comparisons for Multiple Manufacturers and Models

Hybrid vehicle traction driveline gearing has evolved over the last decade or so to match ever increasing speeds for their motors and generators. Auto manufacturers are using increased speed as a means to increase power density of their electric traction motors in vehicles. Oak Ridge National Laboratory (ORNL) is also pursuing traction motor designs that have much higher maximum rotor speeds, in the range of 15,000 – 25,000 rpm.

Ayers, Curtis William↗
DOE OSTI2013

Review of July 2013 Nuclear Security Insider Threat Exercise November 2013

This document is a review of the Nuclear Security Insider Threat Exercise which was hosted at ORNL in July 2013. Nuclear security culture and the insider threat are best learned through experience. Culture is inherently difficult to teach, and as such is best learned through modeled behaviors and learning exercise. This TTX, NSITE, is a tool that strives to aid students in learning what an effective (and ineffective) nuclear security culture might look like by simulating dynamic events that strengthen or weaken the nuclear security regime. The goals of NSITE are to stimulate complex thought and discussion and assist decision makers and management in determining the most effective policies and procedures for their country or facility.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2014

Neutron Scattering Studies of Liquid on or Confined in Nano- and Mesoporous Carbons, Including Carbide-Derived Carbons

This project involved the synthesis of microporous graphitic-carbon powders with subnanometer average pore size, and very narrow pore size distributions, and the use of these materials in experimental studies of pore-fluid structure and dynamics. Samples of carbide-derived carbon powder, synthesized by extraction of the metal cations from TiC by a high temperature chlorination process, followed by high temperature vacuum annealing, were prepared by Ranjan Dash and his associates at CRADA partner Y-Carbon, Inc. The resulting material had average pore sizes ranging from 5 to 8 . These powders were used in two experiments conducted by researchers involved in the Energy Frontier Research Center Directed by David J. Wesolowski at ORNL, the Fluid Interface Reactions, Structures and Transport (FIRST) Center. FIRST-funded researchers at Drexel University collaborated with scientists at the Paul Scherrer Institute, Switzerland, to measure the expansion and contraction of the microporous carbon particles during charging and discharging of supercapactor electrodes composed of these particles (Hantell et al., 2011, Electrochemistry Communications, v. 13, pp. 1221-1224.) in an electrolyte composed of tetraethylammonium tetrafluoroborate dissolved in acetonitrile. In the second experiment, researchers at Oak Ridge National Laboratory and Drexel University conducted quasielastic neutron scattering studies of the diffusional dynamics of water imbibed into the micropores of the same material (Chathoth et al., 2011, EuroPhysics Journal, v. 95, pp. 56001/1-6). These studies helped to establish the role of pores approaching the size of the solvent and dissolved ions in altering diffusional dynamics, ion transport and physical response of conducting substrates to ion desolvation and entry into subnamometer pores.

Fluid Interface Reactions↗
DOE OSTI2014

X-Ray Diffraction of Slag-Based Sodium Salt Waste Forms

Cementitious materials are used to solidify and stabilize aqueous based radioactive waste containing sodium salts. The types and proportions of cementitious ingredients used to treat aqueous radioactive waste streams containing sodium salts depend on the performance objectives for the waste forms and the compositions of the waste streams. Matrix phases can stabilize certain contaminants (co-precipitation, substitution, ion exchange, and / or sorption), influence processing properties, and are responsible for physical properties and durability of the cured waste forms. Consequently, characterization of the matrix (binder) mineralogy (chemical compositions and crystalline / non crystalline structures) is important for predicting contaminant leaching and evolution of the materials as a function of time and changing conditions This report documents sample preparation and x-ray diffraction results for a series of mixtures of sodium salt waste and cementitious binders. The objective of this study was to provide initial phase characterization for the CBP reference case cementitious salt waste form. This information can be used to: 1) generate a base line for the evolution of the waste form as a function of time and conditions, 2) potentially to design new binders based on mineralogy of the binder, 3) understand and predict anion and cation leaching behavior of contaminants of concern, and 4) predict performance of the waste forms for which phase solubility and thermodynamic data are available. Characterization of the mineralogy is also important for understanding the buffering effects that the waste form has on infiltrating water / leachates. More specifically, identification of hydrated phases capable of sequestering anions in the structures and crystallinity of the calcium silicate binder phases were of particular interest. The intent was to use this characterization data as a starting point for more detailed phase characterization using neutron diffraction techniques in addition to quasi-elastic neutron scattering techniques for characterization of water at the ORNL Spallation Neutron Source, Oak Ridge, TN. The initial characterization is complete. Due to extensive substitutions of cations and anions in the layered double hydroxide phases and the very fine intermixing of poorly crystalline hydrated phases in the reference case blend (10 : 45 : 45 cement : slag : fly ash), electron diffraction and transmission electron spectroscopy are recommended as the next step for characterization. In summary, the hydrated mixtures of Type II portland cement, Grade 100 ground granulated blast furnace slag (GGBFS) and carbon burn-out (CBO) Class F Fly ash contained hydrated phase assemblages which were typical of those reported in the literature. Based on x-ray diffraction results, no significant differences were detected in samples cured 2 months and 14 months in sealed containers at ambient indoor temperatures.

36 MATERIALS SCIENCE↗
DOE OSTI2014

Scale-up of Novel Low-Cost Carbon Fibers Leading to High-Volume Commercial Launch

The project started in September, 2012 with the goal of scaling up from the existing laboratory scale process for producing carbon fiber (CF) from polyolefin (PO) based precursor fiber using a Dow proprietary sulfonation-desulfonation stabilization process. The award was used to develop a process that was capable of producing market development quantities of CF from PO precursor fiber at a rate of 4 kg/h of CF. The CF would target properties that met or exceeded the Department of Energy (DOE) Vehicles Technology [1] standard; i.e., 172 GPa modulus and 1.72 GPa strength at greater than or equal to 1% strain. The Dow proprietary process was capable of meeting and exceeding these targets properties. Project DE-EE0005760 resulted from a Collaborative Research and Development Agreement (CRADA) between Dow and Oak Ridge National Laboratory (ORNL) with support from the Michigan Economic Development Corporation (MEDC) and DOE. In the first budget period, the main goal was to design a sulfonation-desulfonation market development plant capable of stabilizing PO precursor fiber at a rate of 5 kg/h using a sulfonation solution. The detailed design, location, and cost estimate were determined as scheduled in the Project Management Plan (PMP). In parallel with this DOE award project was a fundamentals and economic evaluation funded by The Dow Chemical Company (Dow). The goal of the Dow sponsored project was to finalize the mass balances, energy balances, and levelized cost to produce CF using the Dow process. A Go-No-Go decision was scheduled in June, 2013 based on the findings of the DOE sponsored scale up project and the Dow sponsored project. In June, 2013, Dow made the No-Go decision to halt and abandon the Dow proprietary sulfonation-desulfonation process for stabilizing PO precursor fibers for the manufacturing of CF. This No-Go decision was identified in the original proposal and at the start of this project, and the decision was made as scheduled. The decision was based on the high levelized economic cost of the process relative to the manufacture of CF from polyacrylonitrile (PAN) precursor fibers. The capital required to sulfonate the fibers adds a significant cost to the process due to the need for investment in a sulfuric acid recovery plant. This high additional capital over the capital for a PAN based CF plant, reduces the levelized economic cost to slightly advantaged over PAN based CF. The sulfonation-desulfonation stabilization route failed to meet the Dow’s return on investment criterion and the cost advantage target set forth for the DOE project. The DOE and Dow decided to halt spending on the project until a new PO fiber stabilization process could be identified that met the DOE physical properties standard and the levelized economic cost constraints of Dow. When the new technology was developed, then award DE-EE0005760 would be re-started with the same goals of the development of a market development plant capable of producing CF at 4 kg/h with the properties that met or exceed those set forth by the Department of Energy Vehicles Technology standard. Progress on the development of the new process has been slow and thus has delayed the scale up project. Dow’s efforts to date have not progressed to the point of demonstrating a commercially-viable process for production of low cost CF from PO precursors for Dow’s rigorous economic constraints. After extensive discussions within Dow and consultation with DOE’s Advanced Manufacturing Office (AMO) Headquarters and Golden Field Office teams, Dow has decided to proceed with the formal recommendation to terminate subject project. DOE’s AMO Headquarters and Golden Field Office teams agreed with the termination of the project.

36 MATERIALS SCIENCE↗
DOE OSTI2014

High Specific Activity Sm-153 By Post Irradiation Isotope Separation (Final Scientific Technical Report)

The isotope, samarium-153 ( 153 Sm) has ideal nuclear properties well suited for a variety of therapeutic applications; however, it is only available with low specific activity (radioactivity per unit mass) due to the method of production. Commercially useful quantities can be made by the 152 Sm (n,γ) 153 Sm reaction in a nuclear reactor, but typical irradiation parameters result in less than 2% of the 152 Sm target material being converted, leading to a very diluted end product. Since chemical processing methods cannot be used to perform isotopic separation, this means that >98% of the resultant pharmaceutical molecules are labeled with “cold” target atoms and are incapable of providing any radiation-induced therapeutic effect. The goals of this project were to introduce a new approach to the production of high specific activity (HSA) 153 Sm utilizing electromagnetic isotope separation (EMIS), and to perform biodistribution and chemistry studies with such HSA 153 Sm to test labeling capability with targeting molecules. Included in these studies was the successful development of a collection substrate that would allow the efficient deposit and removal of 153 Sm; to this end, DLC (diamond like carbon) foils were successfully employed. In the first year of this project a surface ion source was developed, leading to the successful production of a mass separated beam of stable Sm ions. Studies were then performed using similar apparatus at the Oak Ridge National Laboratory, leading to a well-separated beam of isotopically pure samarium ions. This was followed by the successful production of four 15 mCi samples (over a 7 month period) of HSA 153 Sm which were delivered to the IsoTherapeutics Group for biodistribution and chemical labeling studies. Such samples were produced by neutron irradiation of 5 mg metal samples of 152 Sm at the HFIR (ORNL High Flux Isotope Reactor), followed by manual transfer of the samples from the irradiation capsule to the chamber of a surface ion source. Isotopic beams were then extracted using the IRIS2 EMIS facility, and collected onto 10 μm thick DLC foils. The samples were irradiated for 10 h periods, with typical collection periods lasting 12 - 16 h. Employing appropriate chemical approaches, these HSA 153 Sm samples were evaluated for labeling with small, medium and large molecules. The ability to label a variety of targeting molecules is important to demonstrate the potential therapeutic capabilities. Biodistribution studies, using HSA 153 Sm with the bone agent DOTMP, in rodents demonstrated that the biodistribution is similar to what is observed with LSA 153 Sm. Labeling was successfully achieved with peptides, and large protein molecules.

07 ISOTOPE AND RADIATION SOURCES↗
DOE OSTI2013

Annual Report FY2013-- A Kinematically Complete, Interdisciplinary, and Co-Institutional Measurement of the 19F(α,n) Cross-section for Nuclear Safeguards Science

The goal of this proposal is to enable neutron detection for precision Non-Destructive Assays (NDAs) of actinide-fluoride samples. Neutrons are continuously generated from a UFx matrix in a container or sample as a result of the interaction of alpha particles from uranium-decay α particles with fluorine nuclei in the matrix. Neutrons from 19F(α,n)22Na were once considered a poorly characterized background for assays of UFx samples via 238U spontaneous fission neutron detection [SMI2010B]. However, the yield of decay-α-driven neutrons is critical for 234,235U LEU and HEU assays, as it can used to determine both the total amount of uranium and the enrichment [BER2010]. This approach can be extremely valuable in a variety of safeguard applications, such as cylinder monitoring in underground uranium storage facilities, nuclear criticality safety studies, nuclear materials accounting, and other nonproliferation applications. The success of neutron-based assays critically depends on an accurate knowledge of the cross section of the (α,n) reaction that generates the neutrons. The 40% uncertainty in the 19F(α,n)22Na cross section currently limits the precision of such assays, and has been identified as a key factor in preventing accurate enrichment determinations [CRO2003]. The need for higher quality cross section data for (α,n) reactions has been a recurring conclusion in reviews of the nuclear data needs to support safeguards. The overarching goal of this project is to enable neutron detection to be used for precision Non- Destructive Assays (NDAs) of actinide-fluoride samples. This will significantly advance safeguards verification at existing declared facilities, nuclear materials accounting, process control, nuclear criticality safety monitoring, and a variety of other nonproliferation applications. To reach this goal, Idaho National Laboratory (INL), in partnership with Oak Ridge National Laboratory (ORNL), Rutgers University (RU), and the University of Notre Dame (UND), will focus on three specific items: (1) making a precision (better than 10 %) determination of the absolute cross section of the 19F(α,n)22Na reaction as a function of energy; (2) determining the spectrum of neutrons and γ-rays emitted from 19F(α,n)22Na over an energy range pertinent to NDA; and (3) performing simulations with this new cross section to extract the neutron yield (neutrons/gram/second) and resulting neutron- and gamma ray-spectra when α particles interact with fluorine nuclei in actinide samples, to aid in the design and reduce uncertainty of future NDA measurements and simulations.

VANDLE, HPGe gamma-ray detector, liquid neutron de↗
DOE OSTI2014

Application of Super-Hydrophobic Coating for Enhanced Water Repellency of Ballistic Fabric

The objective of this work was to demonstrate that a superhydrophobic coating technology developed at Oak Ridge National Laboratory (ORNL) increases the water repellency of ballistic fabric beyond that provided by existing water repellency treatments. This increased water repellency has the potential to provide durable ballistic fabric for body armor without adding significant weight to the armor or significant manufacturing cost. Specimens of greige and scoured ballistic fabric were treated with a superhydrophobic coating and their weights and degree of water repellency were compared to specimens of untreated fabric. Treatment of both greige and scoured ballistic fabrics yielded highly water repellent fabrics. Our measurements of the water droplet contact angles gave values of approximately 150 , near the lower limit of 160 for superhydrophobic surfaces. The coatings increased the fabric weights by approximately 6%, an amount that is many times less than the estimated weight increase in a conventional treatment of ballistic fabric. The treated fabrics retained a significant amount of water repellency following a basic abrasion test, with water droplet contact angles decreasing by 14 to 23 . Microscopic analysis of the coating applied to woven fabrics indicated that the coating adhered equally well to fibers of greige and scoured yarns. Future evaluation of the superhydrophobic water repellent treatment will involve the manufacture of shoot packs of treated fabric for ballistic testing and provide an analysis of manufacturing scale-up and cost-to-benefit considerations.

superhydrophobic water repellent coating treatment↗
DOE OSTI2014

Perform Tests and Document Results and Analysis of Oxide Layer Effects and Comparisons

During the initial feasibility test using actual used nuclear fuel (UNF) cladding in FY 2012, an incubation period of 30–45 minutes was observed in the initial dry chlorination. The cladding hull used in the test had been previously oxidized in a dry air oxidation pretreatment prior to removal of the fuel. The cause of this incubation period was attributed to the resistance to chlorination of an oxide layer imparted by the dry oxidation pretreatment on the cladding. Subsequently in 2013, researchers at the Korea Atomic Energy Institute (KAERI) reported on their chlorination study [R1] on ~9-gram samples of unirradiated ZirloTM cladding tubes that had been previously oxidized in air at 500oC for various time periods to impart oxide layers of varying thickness. In early 2014, discussions with Indefinite Delivery, Indefinite Quantity (IDIQ) contracted technical consultants from Westinghouse described their previous development (and patents) [R2] on methods of chemical washing to remove some or all of the hydrous oxide layer imparted on UNF cladding during irradiation in light water reactors (LWRs) . Thus, the Oak Ridge National Laboratory (ORNL) study, described herein, was planned to extend the KAERI study on the effects of anhydrous oxide layers, but on larger ~100-gram samples of unirradiated zirconium alloy cladding tubes, and to investigate the effects of various methods of chemical pretreatment prior to chlorination with 100% chlorine on the average reaction rates and Cl2 usage efficiencies.

Korea Atomic Energy Institute (KAERI)↗
DOE OSTI2014

Cryptographic Key Management System (CKMS)

This report summarizes the outcome of U.S. Department of Energy (DOE) contract DE-OE0000543, requesting the design of a Cryptographic Key Management System (CKMS) for the secure management of cryptographic keys for the energy sector infrastructure. Prime contractor Sypris Electronics, in collaboration with Oak Ridge National Laboratories (ORNL), Electric Power Research Institute (EPRI), Valicore Technologies, and Purdue University's Center for Education and Research in Information Assurance and Security (CERIAS) and Smart Meter Integration Laboratory (SMIL), has designed, developed and evaluated the CKMS solution. We provide an overview of the project in Section 3, review the core contributions of all contractors in Section 4, and discuss benefits to the DOE in Section 5. In Section 6 we describe the technical construction of the CKMS solution, and review its key contributions in Section 6.9. Section 7 describes the evaluation and demonstration of the CKMS solution in different environments. We summarize the key project objectives in Section 8, list publications resulting from the project in Section 9, and conclude with a discussion on commercialization in Section 10 and future work in Section 11.

97 MATHEMATICS AND COMPUTING↗
DOE OSTI2014

Determine Minimum Silver Flake Addition to GCM for Iodine Loaded AgZ

The minimum amount of silver flake required to prevent loss of I{sub 2} during sintering in air for a SNL Glass Composite Material (GCM) Waste Form containing AgI-MOR (ORNL, 8.7 wt%) was determined to be 1.1 wt% Ag. The final GCM composition prior to sintering was 20 wt% AgI-MOR, 1.1 wt% Ag, and 80 wt% Bi-Si oxide glass. The amount of silver flake needed to suppress iodine loss was determined using thermo gravimetric analysis with mass spectroscopic off-gas analysis. These studies found that the ratio of silver to AgI-MOR required is lower in the presence of the glass than without it. Therefore an additional benefit of the GCM is that it serves to inhibit some iodine loss during processing. Alternatively, heating the AgI-MOR in inert atmosphere instead of air allowed for densified GCM formation without I{sub 2} loss, and no necessity for the addition of Ag. The cause of this behavior is found to be related to the oxidation of the metallic Ag to Ag{sup +} when heated to above ~300{degrees}C in air. Heating rate, iodine loading levels and atmosphere are the important variables that determine AgI migration and results suggest that AgI may be completely incorporated into the mordenite structure by the 550{degrees}C sintering temperature.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2014

Final report for next generation multi-scale quantum simulation software for strongly correlated materials

The goal of this project was to develop a new formalism for the correlated electron problem, which we call, the Multi Scale Many Body formalism. This report will focus on the work done at the Louisiana State University (LSU) since the mid term report. The LSU group moved from the University of Cincinnati (UC) to LSU in the summer of 2008. In the last full year at UC, only half of the funds were received and it took nearly two years for the funds to be transferred from UC to LSU . This effectively shut down the research at LSU until the transfer was completed in 2011, there were also two no-cost extensions of the grant until August of this year. The grant ended for the other SciDAC partners at Davis and ORNL in 2011. Since the mid term report, the LSU group has published 19 papers [P1-P19] acknowledging this SciDAC, which are listed below. In addition, numerous invited talked acknowledged the SciDAC. Below, we will summarize the work at LSU since the mid-term report and mainly since funding resumed. The projects include the further development of multi-scale methods for correlated systems (1), the study of quantum criticality at finite doping in the Hubbard model (2), the description of a promising new method to study Anderson localization with a million-fold reduction of computational complexity!, the description of other projects (4), and (5) a workshop to close out the project that brought together exascale program developers (Stellar, MPI, OpenMP,...) with applications developers.

97 MATHEMATICS AND COMPUTING↗