The American Diabetes Association (ADA) and the European Association for the Study of Diabetes (EASD) convened a writing group to develop a consensus statement on the management of type 1 diabetes in adults. The writing group has considered the rapid development of new treatments and technologies and addressed the following topics: diagnosis, aims of management, schedule of care, diabetes self-management education and support, glucose monitoring, insulin therapy, hypoglycemia, behavioral considerations, psychosocial care, diabetic ketoacidosis, pancreas and islet transplantation, adjunctive therapies, special populations, inpatient management, and future perspectives. Although we discuss the schedule for follow-up examinations and testing, we have not included the evaluation and treatment of the chronic microvascular and macrovascular complications of diabetes as these are well-reviewed and discussed elsewhere. The writing group was aware of both national and international guidance on type 1 diabetes and did not seek to replicate this but rather aimed to highlight the major areas that health care professionals should consider when managing adults with type 1 diabetes. Though evidence-based where possible, the recommendations in the report represent the consensus opinion of the authors.
Frontier Technology Inc., Beavercreek, Ohio, has been awarded a $55,517,773 cost-plus-fixed-fee modification P00037 to previously awarded contract FA8806-19-C-0004 for life cycle decision support. The contract modification provides for support and analysis to aid in the rapid prototyping and delivery of enterprise ground services to future and existing U.S. Space Force missions. Work will be performed in Colorado Springs, Colorado, and is expected to be completed by Aug. 4, 2024. Fiscal 2021 research, development, test and evaluation funds in the amount of $1,290,330 are being obligated at the time of award. The total cumulative face value of the contract is $165,077,137. Space Systems Command, Los Angeles Air Force Base, California, is the contracting activity.
Rapid Rig Advanced 21
UES Inc., Dayton, Ohio, has been awarded a $20,000,000 cost-plus-fixed-fee completion-type task order (FA8650-21-F-5280) off of a $49,900,000 indefinite-delivery/indefinite-quantity contract (FA8650-21-D-5279) for research in the area of advanced ceramic and composite materials and process development. The contract provides for the materials, processing methodologies and an understanding of their behavior to create advanced components for application in future Air Force weapon systems. Work will be performed at Wright-Patterson Air Force Base, Ohio, and is expected to be completed by Dec. 29, 2025. This award is the result of a closed, one-step broad agency announcement in which two offers were received. Fiscal 2021 research, development, test and evaluation funds in the amount of $933,500 will be obligated at the time of award. Air Force Research Laboratory, Wright-Patterson Air Force Base, Ohio, is the contracting activity.
The "advanced" elements of an ADMS go beyond traditional distribution management systems by providing next-generation control capabilities. These capabilities include the management of high penetrations of distributed energy resources (DERs), closed-loop interactions with building management systems, and tighter integration with utility tools for meter data management systems, asset data, and billing.
This platform can be integrated with the ADMS test bed to evaluate the performance of novel ADMS applications. By reducing the cost and complexity of deployment, and by quantifying the operational benefits, barriers to widespread deployment will be eliminated. The GridAPPS-D platform provides a data rich control environment for researchers to develop futuristic advanced distribution applications, which include the following examples: increased efficiency, reliability, and resilience with real-time DER dispatch; short-term grid forecasting, which has the capacity to pave the way for developing market-based approach to manage distribution assets and flexible resources; and solar forecasting that provides intra-hour forecasted data for DSO to include the impact of solar PV for making operational planning decisions.
The first layer of defense, the security situational awareness, supports the operator in the microgrid management system to (1) assess the power system's resilience with appropriate metrics based on solar situational awareness; (2) suggest preemptive measures to increase the resilience prior to anticipated physical threats, such as natural disasters; and (3) detect, localize, and find the root cause of cyberattacks. Security situational awareness will use advanced data analytics and power flow optimization methods.
The second module is online multi-objective optimization, an advanced algorithm that communicates with asynchronous devices in the system, such as capacitor bands and PV arrays, to dispatch devices at different timescales. The result is the capability to operate and control up to tens of millions of solar energy arrays through a fraction of devices in a proactive fashion.
In February 2019 the US Department of Energy launched its Versatile Test Reactor (VTR) programme, set up under the Nuclear Energy Innovation Capabilities Act 2017 and run by the Idaho National Laboratory. The VTR project is to be a research facility for testing of advanced nuclear fuels, materials, instrumentation and sensors. It is to provide accelerated neutron damage rates 20 times greater than current water-cooled test reactors. GE Hitachi's PRISM will be adapted as a test reactor under this programme for R&D. Operation is planned by the end of 2025.
India's nuclear power program has been focused on developing an advanced heavy-water thorium cycle, based on converting abundant thorium-232 into fissile uranium-233. The first stage of this employs PHWRs fuelled by natural uranium, and light water reactors, to produce plutonium. Stage two uses fast neutron reactors burning the plutonium to breed U-233 from thorium. The blanket around the core will have uranium as well as thorium, so that further plutonium (ideally high-fissile Pu) is produced as well as the U-233. Then in stage three, advanced heavy water reactors burning the U-233 and this plutonium as driver fuels, but utilising thorium as their main fuel, and getting about two-thirds of their power from the thorium.
It will be 2800 MW thermal at 550C, giving 1220 MWe gross and 60-year lifetime (30 years for steam generators), with burn-up of up to 120 GWd/t (average 90 GWd/t for nitride, 112 for MOX). Intermediate heat exchanger temperature 550C, with 527C in secondary sodium circuit and 510C outlet at 17 MPa from steam generators which represent an advanced design. Thermal efficiency is 43.5% gross, 40.7% net. Simplified refuelling is on a 330-day cycle (cf 155 days for BN-800). The initial loading of fissile plutonium isotopes is 7.5 tonnes, usage per year 8.74 tonnes of fuel, including 1.39 tonnes of plutonium. Fuel loading is 47 t of MOX, or 59 t nitride. Concentration of fissile plutonium is 16%. Core breeding ratio was intended to be 1.2 initially with MOX fuel, later 1.35, and then 1.45 with nitride fuel, but has been reduced to about 1, with nitride fuel. Fuel burn-up is designed to progress from 14.3% to 21%. It would have 426 fuel assemblies and 174 radial blanket assemblies surrounded by 599 boron shielding assemblies. Spent fuel assemblies would be stored in the reactor for two years.
Phase 2 of the study focused on four basic reactor designs: sodium-cooled with MOX and metal fuels, helium-cooled with nitride and MOX fuels, lead-bismuth eutectic-cooled with nitride and metal fuels, and supercritical water-cooled with MOX fuel. All involve closed fuel cycle, and three reprocessing routes were considered: advanced aqueous, oxide electrowinning and metal pyroprocessing (electrorefining). This work is linked with the Generation IV initiative, where Japan is playing a leading role with sodium-cooled FBRs.
Closely related to its major research initiative on an advanced spent fuel conditioning process (ACP), and designed to be fuelled by the product of it, KAERI has proposed development of a pool-type sodium-cooled fast reactor, which will operate in burner (not breeder) mode. ACP will use electrometallurgical pyroprocessing to close the fuel cycle with oxide fuels which have been reduced to the metal on a commercial basis. (The pulverised used fuel is heated to drive off volatile fission products and then it is reduced to metal.) In a bath of molten lithium and potassium chloride, uranium is recovered electrolytically. The remaining tranuranics (Pu, Np, Am, Cm) are concentrated and removed with the remaining fission products (notably cerium, neodymium & lanthanum) to be fabricated into fast reactor fuel without any further treatment. This is intrinsically proliferation-resistant because it is so hot radiologically, and the curium provides a high level of spontaneous neutrons. Also it recycles about 95% of the used fuel. The ACP Facility (ACPF) at KAERI was built in the basement of the Irradiated Materials Experiment Facility (IMEF) for laboratory-scale demonstration of ACP.
While General Atomics worked on the design in the 1970s (but not as fast reactor), none has so far been built. The French Atomic Energy Commission (CEA) is well advanced in design of ALLEGRO on behalf of Euratom. It will incorporate all the architecture and the main materials and components foreseen for the GFR without the power conversion system.
Lead-cooled fast reactors. Liquid metal (Pb or Pb-Bi) cooling is by natural convection. Fuel is depleted uranium metal or nitride, with full actinide recycle from regional or central reprocessing plants. A wide range of unit sizes is envisaged, from factory-built "battery" with 15-20 year life for small grids or developing countries, with circulation by convection, to modular 300-400 MWe units and large single plants of 1400 MWe. Operating temperature of 550C is readily achievable but 800C is envisaged with advanced materials and this would enable thermochemical hydrogen production. 2ff7e9595c
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