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Susannah Tringe of the DOE Joint Genome Institute talks about the Program Overview and Program Informatics at the Metagenomics Informatics Challenges Workshop held at the DOE JGI on October 12-13, 2011.
Linear programming techniques applied to human reliability in space programs - optimization of crew tasks
Space exploration programs and space science - lunar and planetary-interplanetary programs, deep space network, and supporting activities
The Mars Exploration Program and constituent Mars Technology Program are described. Current ongoing and future NASA-led missions are presented, including discussions of scientific accomplishments and objectives as well as technology validations accomplished and technological enablers for future missions.
The Alternative and Renewable Fuel and Vehicle Technologies Program (ARFVTP) supports a wide range of alternative, low-carbon fuel and vehicle projects in California. This report focuses on two types of ARFVTP benefits. Expected benefits reflect successful deployment of vehicles and fuels supported through program projects. Market transformation benefits represent benefits resulting from project influences on future market conditions to accelerated technology adoption rates. Data collected directly from ARFVTP projects funded from 2009 to first quarter 2014 are used as inputs to the benefits analysis, where possible. Expected benefit estimation methods rely primarily upon project-level data and result in year single-point estimates within the 2011 to 2025 analysis period. Results suggest that the 178 projects evaluated for expected benefits, representing an investment of $351.3 million in ARFVTP funds, could result in a reduction in petroleum fuel use by 236 million gallons per year and greenhouse gases (GHGs) by 1.7 million metric tonnes carbon dioxide equivalent (MMTCO2e) per year by 2025. Market transformation benefits are described as accruing in addition to expected benefits. They are inherently more uncertain and theoretical than expected benefits, and are therefore reported as high and low ranges, with results suggesting reductions of 1.1 MMTCO2e to 2.5 MMTCO2e per year in GHG reductions and 102 million to 330 million gallons per year in petroleum fuel reductions by 2025. Taking both benefit types into account, results suggest that ARFVTP projects have the potential to make substantial progress toward meeting California's long-term GHG and petroleum fuel use reduction goals. As additional project data become available and market success with alternative and renewable fuels and vehicles grows, the analytic framework relied upon to develop these estimates will become more rigorous and will have a greater capacity to inform future ARFVTP activities.
This program provides practical training to DHS graduate fellows in the DOE laboratory complex. It involves coordinating students, their thesis advisors, and their laboratory project mentors in establishing a meaningful program of research which contributes to the graduate student's formation as a member of the nuclear forensics community. The summary report details the student/mentor experience and future plans after the first summer practicum.
Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline - even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy's Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration's energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program's plans.
Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy’s Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program’s plans.
The Better Buildings Neighborhoods Program Final Report: Maryland’s Be SMART Program
The IDCA conducted a program review at Los Alamos National Laboratory, September 14 and 15, 2010. The review was divided into three parts: 1) an update on the current status of the program, 2) an information exchange and discussion on technical details for current issues and future planning, and 3) a tour of the SSST testing facilities at LANL. The meeting started with an update from DHS by Laura Parker and a restating of some of the objectives of the Proficiency Test of which the IDCA is currently engaged. This update was followed by a discussion of some high level programmatic issues particularly about ways of communicating the overall goals of the IDCA to non-technical representatives. The final topic focused on the difficulty of releasing information, including the DHS approval process, ITAR, and open publication. Next JGR presented a technical summary of accomplishments, schedule, milestones, and future directions. These key points made were: 1) about 1/3 of the materials have been tested, 2) some participants are behind others causing a lag in report writing, 3) method reports have been assigned to various participants to speed up the process of reporting, 4) the SSST Compendium needs reformatting and restructuring, and 5) the Compendium needs a web site to house with access control. After the technical update, some of the Proficiency Test results were shown comparing data from the various laboratories. These results included comparisons of the RDX standard, KC/sugar mixtures (-100 mesh and as received), KC/dodecane, KP/Al, and KP/C. Impact, friction, ESD, and DSC results were the focus. All the participants were involved in these discussions. This report includes summary notes, presentations, and explanatory information.
This presentation covers the Nuclear Criticality Safety Program (NCSP) training & education program. The presentation details the training courses offered by the NCSP and the NCSP training pipelines. Additionally, the presentation shows the Nuclear Criticality Safety (NCS) Education Training (NCSET) modules along with new capabilities and new courses. This lecture finishes up with some concluding remarks.
Space exploration programs and science - Surveyor project, Mariner program, Deep Space Instrumentation Facility, space flight operation facility, environment test facility, and physics
This case study from DOE’s Home Upgrade Program Accelerator highlights process improvements undertaken by Build It Green and Pacific Gas & Electric to streamline California's Home Energy Program. These improvements are intended to result in fewer errors and more reliable predicted energy savings.
Task parallelism is an attractive approach to automatically load balance the computation in a parallel system and adapt to dynamism exhibited by parallel systems. Exploiting task parallelism through work stealing has been extensively studied in shared and distributed-memory contexts. In this paper, we study the design of a system that uses work stealing for dynamic load balancing of task-parallel programs executed on hybrid distributed-memory CPU-graphics processing unit (GPU) systems in a global-address space framework. We take into account the unique nature of the accelerator model employed by GPUs, the significant performance difference between GPU and CPU execution as a function of problem size, and the distinct CPU and GPU memory domains. We consider various alternatives in designing a distributed work stealing algorithm for CPU-GPU systems, while taking into account the impact of task distribution and data movement overheads. These strategies are evaluated using microbenchmarks that capture various execution configurations as well as the state-of-the-art CCSD(T) application module from the computational chemistry domain
Background: Neuroprotection for Parkinson Disease (PD) remains elusive. Biomarkers hold the promise of removing roadblocks to therapy development. The National Institute of Neurological Disorders and Stroke (NINDS) has therefore established the Parkinson’s Disease Biomarkers Program (PDBP) to promote discovery of biomarkers for use in phase II-III clinical trials in PD. Methods: The PDBP facilitates biomarker development to improve neuroprotective clinical trial design, essential for advancing therapeutics for PD. To date, eleven consortium projects in the PDBP are focused on the development of clinical and laboratory-based PD biomarkers for diagnosis, progression tracking, and/or the prediction of prognosis. Seven of these projects also provide detailed longitudinal data and biospecimens from PD patients and controls, as a resource for all PD researchers. Standardized operating procedures and pooled reference samples have been created in order to allow cross-project comparisons and assessment of batch effects. A web-based Data Management Resource facilitates rapid sharing of data and biosamples across the entire PD research community for additional biomarker projects. Results: Here we describe the PDBP, highlight standard operating procedures for the collection of biospecimens and data, and provide an interim report with quality control analysis on the first 1082 participants and 1033 samples with quality control analysis collected as of October 2014. Conclusions: By making samples and data available to academics and industry, encouraging the adoption of existing standards, and providing a resource which complements existing programs, the PDBP will accelerate the pace of PD biomarker research, with the goal of improving diagnostic methods and treatment.
The multicore generation of scientific high performance computing has provided a platform for the realization of Exascale computing, and has also underscored the need for new paradigms in coding parallel applications. The current standard for writing parallel applications requires programmers to use languages designed for sequential execution. These languages have abstractions that only allow programmers to operate on the process centric local view of data. To provide suitable languages for parallel execution, many research efforts have designed languages based on the Partitioned Global Address Space (PGAS) programming model. Chapel is one of the more recent languages to be developed using this model. Chapel supports multithreaded execution with high-level abstractions for parallelism. With Chapel in mind, we have developed a set of directives that serve as intermediate expressions for transitioning scientific applications from languages designed for sequential execution to PGAS languages like Chapel that are being developed with parallelism in mind.
Under the US Fusion Nuclear Science and Technology program, we selected the Dual Coolant Lead Lithium (DCLL) concept as our primary Test Blanket Module (TBM) for testing in ITER. The DCLL blanket concept has the potential to be a high-performance DEMO blanket design with a projected thermal efficiency of >40%. Reduced activation ferritic/martensitic (RAF/M) steel is used as the structural material. Helium is used to cool the first wall and blanket structure, and the self-cooled Pb-17Li breeder is circulated for power conversion and for tritium extraction. A SiC-based flow channel insert (FCI) is used as an electrical insulator for magnetohydrodynamic pressure drop reduction from the circulating Pb-17Li and as a thermal insulator to separate the high-temperature Pb-17Li (~650–700 °C) from the RAF/M structure, which has a corrosion temperature limit of ~480 °C. The RAF/M material must also operate at temperatures above 350 °C but less than 550 °C. We are continuing the development of the mechanical design and performing neutronics, structural and thermal hydraulics analyses of the DCLL TBM module. Prototypical FCI structures were fabricated and further attention was paid to MHD effects and the design of the inboard blanket for DEMO. We are also making progress on related R&D needs to address key areas. Finally, this paper is a summary report on the progress and results of recent DCLL TBM development activities.
The Fuel Cycle Research and Development program is investigating methods of burning minor actinides in a transmutation fuel. One of the challenges of achieving this goal is to develop fuels capable of reaching extreme burnup levels (e.g. 40%). To achieve such high burnup levels’ fast reactor core materials (cladding and duct) must be able to withstand very high doses (>300 dpa design goal) while in contact with the coolant and the fuel. Thus, these materials must withstand radiation effects that promote low temperature embrittlement, radiation induced segregation, high temperature helium embrittlement, swelling, accelerated creep, corrosion with the coolant, and chemical interaction with the fuel (FCCI). To develop and qualify materials to a total fluence greater than 200 dpa requires development of advanced alloys and irradiations in fast reactors to test these alloys. Test specimens of ferritic/martensitic alloys (T91/HT-9) previously irradiated in the FFTF reactor up to 210 dpa at a temperature range of 350– 750 °C are presently being tested. This includes analysis of a duct made of HT-9 after irradiation to a total dose of 155 dpa at temperatures from 370 to 510 °C. Compact tension, charpy and tensile specimens have been machined from this duct and mechanical testing as well as SANS and Mossbauer spectroscopy are currently being performed. Initial results from compression testing and Charpy testing reveal a strong increase in yield stress (~400 MPa) and a large increase in DBTT (up to 230 °C) for specimens irradiated at 383 °C to a dose of 28 dpa. Less hardening and a smaller increase in DBTT was observed for specimens irradiated at higher temperatures up to 500 °C. Advanced radiation tolerant materials are also being developed to enable the desired extreme fuel burnup levels. Specifically, coatings are being developed to minimize FCCI, and research is underway to fabricate large heats of radiation tolerant oxide dispersion steels with homogeneous oxide dispersions.