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The purpose of this CRADA was for LLNL to provide the engineering, design, and component specification of the instrumentation and controls of Elmore Associate's multipoint ignition scheme for liquid gun propellant applications.
he ITER (not an acronym but Latin for "the Way”) International Organization (IO) is building a large-scale scientific experiment that is now under construction in Cadarache, France. The ITER Tokamak fusion reactor aims to demonstrate that it is possible to produce energy from fusion. The ITER’s power output goal is to deliver ten times the power it consumes. During its operational lifetime, ITER will test key technologies necessary for the next step: the demonstration fusion power plant that will prove that it is possible to capture fusion energy for commercial use. General information on the ITER project can be found at http://www.iter.org. The ITER reactor’s superconducting magnet systems create ~41GJ of stored magnetic field energy when fully energized. The consequences of such energy dissipating via electrical arcs under faulted conditions gives rise to safety concerns even though these fault events are extremely unlikely. As part of the ITER licensing procedure, and as a result of such safety concerns, this contract was established to benchmark a developing magnet safety analysis tool at Culham Centre for Fusion Energy against the MAGARC computer code. MAGARC was developed by the U.S. Idaho National Laboratory (INL) under the ITER Engineering Design Activity (EDA) Project and was applied to produce previous analyses, in order to support magnet fault and safety assessment for the ITER design description document. This contract report documents the completion of requested modifications to the MAGARC code by the ITER IO, a time-step size sensitivity analysis with MAGARC during an unmitigated quench event, a comparison of the modeling approaches taken in developing MAGARC and the CCFE analysis package, and the data required for the benchmarking activity for these codes.
The processing of used nuclear fuel releases volatile and semivolatile radionuclides into the off-gas streams associated with the various processing steps. Ongoing efforts to develop methods to control the release of gaseous radionuclides to the environm ent have identified ruthenium (specifically 106 Ru) as one of the semivolatile nuclides requiring a high degree of abatement. The tritium pretreatment process will release a fraction of the ruthenium as volatile ruthenium tetroxide (RuO 4 ). Tests were conducted to examine the deposition phenomena and provide prelim inary information pertinent to an engineering design of a sorption bed to remove RuO 4 from a gas stream (e.g., approximate length of the mass transfer zone and the loading per unit mass of sorbent).
Modern synchrotron lattices follow Multi-Bend Achromat approach and realize low emittance by arranging small horizontal beta-function and dispersion in the bends. In this paper we propose another optics solution aimed to reach low emittance by using a lattice element that we named as “Complex Bend”. The Complex Bend corresponds to a strong alternate focusing distributed along the bend so to maintain the beta-function and dispersion oscillating at low values. Comprising the ring lattice out of Complex Bends instead of regular dipoles will minimize the Ң-function and reduce the horizontal emittance while localizing bending to a small fraction of the storage ring circumference. The latter should help to gain more space for Insertion Devices. In the following, we present the concept of Complex Bend, considerations on the choice of its optimal parameters, as well as, thoughts of its practical realization. This paper gives a snapshot where our current studies stand and does not pretend to be a complete description of the Complex Bend engineering design and integration of this element into a specific ring lattice.
The overall objectives are to provide the science-base needed by industry to understand how emerging alternative fuels impact highly efficient DISI light-duty engines being developed by industry and how engine design and operation can be optimized for most efficient use of future fuels.
The overall objectives are to provide the science-base needed by industry stakeholders to understand how engine design and operation can be co-optimized with future fuels for highest overall system efficiency.
The purpose of this CRADA was to integrate a reduced order model simulation capability into advanced engineering design capabilities. This work contributed to a substantial reduction in the time required to simulate an additive manufacturing process. Shorter simulation time improves the commercial viability and practical utility of the Sunata software and may lead to wider adoption of additive manufacturing processes.
More efficient engines enabled by better fuels derived from biomass could increase the fuel economy of the light duty (LD) fleet by 10% over current technology and planned developments. This report identifies top LD boosted spark ignition (BSI) biofuel candidates for further development and commercialization identified using a fuel property basis. The BSI merit function was used to evaluate the performance of candidate bio-blendstocks in improving engine efficiency. This report is aimed at biofuel researchers looking to better understand the efficiency implications of biofuels under development, as well as engine researchers who are interested in future biofuels with properties that enable more efficient engine design and operation.
As advanced reactor concepts are developed, instrumentation and control (I&C) cables and sensors will play a significant role in assuring their operation is well understood, and safety-related process information can be collected reliably over the course of their design life. As a first step to develop acceptance criteria and define the limits of currently available nuclear I&C cable and sensor technology, a collaboration between Oak Ridge National Laboratory and Analysis and Measurement Services (AMS) Corporation was initiated under the Gateway for Accelerated Innovation in Nuclear (GAIN) Program. This collaborative effort focused on providing technical information related to the combined thermal and radiation aging of nuclear power plant (NPP) cables, companion NPP cable insulation samples, and two prototype temperature and two pressure sensors. This work was carried out using the instrumented gamma irradiation system that is part of the High Flux Isotope Reactor Gamma Irradiation Facility (HFIR GIF). This system provided the opportunity for the condition of the prototype sensors to be tracked during the irradiation in order to determine their functional limits with greater granularity when compared to a simple irradiation insertion at the HFIRGIF. Experimental assemblies for sensor irradiation were successfully completed, and sensor irradiation to accumulated dose of 3000 kGy at a rate of approximately 6 kGy/hr was carried out. Two prototype temperature assemblies were continuously monitored during exposure to 3000 kGy and found to have no observable degradation from the irradiation. Two pressure sensors were first irradiated to 1000 kGy. At which point, one of the sensors was found to operate normally; however, a second sensor failed the operability test. The operable pressure sensor output was then continuously monitored from 1000 kGy to 3000 kGy. The sensor output exhibited steady trendable drift versus the accumulated radiation dose. At the conclusion of the irradiation, the four test sensors were released for laboratory calibration checks. The calibration check of the temperature sensors found no significant change after irradiation compared to baseline measurements before irradiation; however, both pressure sensors failed the post-test calibration checks and both sensors were not functioning properly. These results will help inform sensor manufacturers and I&C design engineers of potential limitations of these types of sensors for use in high radiation environments associated with the compact configuration of new Small Modular Reactors (SMRs) such as NuScale’s reactor power module. Irradiations on NPP cables and companion samples were not completed due to programmatic delays, however a path forward that was based on lessons learned from this project was defined to accommodate future, comparable instrumented gamma irradiations at the HFIR GIF.
The Following Document is the Final Technical Scientific Report for the project tittle “10 MWE CDCL Large Pilot Plant – pre-FEED Study” performed by The Babcock & Wilcox Company in collaboration with The Ohio State University, Johnson & Matthey, The Electric Power Research Institute, and the Dover Light & Power Municipal Power Plant. The project Team performed a pre-Front End Engineering Design study of a 10 MWe Coal-Direct Chemical Looping power plant to be hosted at the Dover Light & Power Municipal Plant. As part of the pre-FEED study, the project Team performed multiple pilot test campaigns to obtain design and performance information at the 250 kWth CDCL pilot facility at the Babcock & Wilcox Company’s Research Center. The Techno-Economic analysis was updated based on the FEED study and the pilot tests results. The study shows that the CDCL process is a promising carbon-friendly technology capable of producing electricity with a high efficiency with a cost of electricity of $83.3 / MWh, which corresponded to less than 30% increase in cost of electricity compared to the cost of electricity of a base case study of a supercritical PC boiler.
Given the steady growth in world population and the ever-increasing fresh water demand, the only sustainable water supply option is desalination. Conceptually, desalination is very simple - just separate dissolved salts from water. While desalination research programs have existed since the 1960s and have resulted in a multitude of approaches, realizing affordable desalination has proven to be a challenge. Our goal is to meet this challenge using low cost heat sources to drive a liquid-discharge-free desalination process that can be co-mingled with the extraction of economically valuable co-products. High temperatures and pressures will be used to manipulate water’s properties, such as the dielectric constant, and hence its ability to solvate ions. Selective precipitation/recovery of valuable metal co-products creates new revenue streams (i.e., cost offsets). We will develop the scientific understanding necessary to control salt precipitation from supercritical seawater, inland brines, and water commonly co-produced with oil and gas. Atomistic simulations will be used to understand at a molecular level the changes in hydrogen bonding and ion solvation that occur as we increase the temperature and/or pressure and change the density and ion concentration. Our simulation results will also aid in the interpretation of experimental data and guide the development of applied thermodynamic models for engineering design calculations.
At Los Alamos, we deliver science and technology to protect our nation and promote world stability Los Alamos National Laboratory. Our mission began by applying science and technology to address an international crisis. Today, we are responsible for the design, engineering, and sustainment of the majority of the United States’ nuclear weapons capabilities. We also work to assess & reduce global nuclear danger. We offer unparalleled career opportunities in science, engineering, manufacturing, business, and more
More efficient engines enabled by better fuels derived from biomass could increase the fuel economy of the light duty (LD) fleet by 10% over current technology and planned developments. This report identifies top LD boosted spark ignition (BSI) biofuel candidates for further development and commercialization identified using a fuel property basis. The BSI merit function was used to evaluate the performance of candidate bio-blendstocks in improving engine efficiency. This report is aimed at biofuel researchers looking to better understand the efficiency implications of biofuels under development, as well as engine researchers who are interested in future biofuels with properties that enable more efficient engine design and operation.
This article is set during the 1944 and 1945 final push to complete Project Y—the Manhattan Project at Los Alamos—and focuses primarily on overcoming the challenge of creating and demonstrating a successful convergent explosive implosion to turn a subcritical quantity of plutonium into a critical mass. The critical mass would then efficiently yield kilotons of trinitrotoluene (TNT)-equivalent energy in about a microsecond, demonstrating the implosion atomic bomb concept. This work culminated in the Trinity atomic test near Alamogordo on July 16, 1945. This implosion effect demarcated the approach to explosive science and technology the Laboratory has followed ever since, including development of high-explosive synthesis and formulation, small and large test and diagnostic facilities, shock dynamics theory, high-explosive system design engineering, and three-dimensional implosion modeling and simulation using some of the fastest computers in the world. This work also ushered in a period of broader application of precision high explosives in conventional munitions, demolition, mining and oil exploration, and space travel.
Detonator Production and Prototype Fabrication divisions serve a variety of organizations throughout the Laboratory and the nation by providing key non-nuclear components through excellence in on-site engineering, design, manufacturing, machining, and more.
This project produced clear evidence that biofuels can reduce particulate emissions from road vehicles compared with petroleum-derived fuels. It also produced fundamental knowledge that can be used to select fuel compositions and engine designs that will maximize this benefit. This information has been disseminated through more than 20 peer-reviewed publications, more than 30 conference presentations, and 5 freely available internet databases and web tools. This project also provided educational opportunities to 17 students at the high school, undergraduate, and graduate levels.
Research and development that supports the management of off-gases from nuclear fuel reprocessing has historically been focused on the off-gas streams that arise from aqueous reprocessing technology. However, as Gen-IV reactor development pathways move toward deployment, alternative spent nuclear fuel (SNF) processing and disposition pathways have been considered more actively. This work is focused upon aspects of fluoride volatility (FV) processing. The versatility of this method for deployment against multiple types of spent fuel encourages the continued advancement of both the primary separations processes and the secondary processes, including waste treatment, material control and accountability, and engineering designs. Recent work noted that TeF 6 , the most highly volatile fluorinated compound produced during FV processing, did not have a clear abatement technology recommended in the literature. Thus, this work performed scoping tests on activated alumina and copper shot to assess whether they could be used to remove TeF 6 from gas streams that bear F 2 . Previous work on this topic was not well described in the literature and was not performed with excess F 2 in the stream as would be typical of spent fuel processing via FV. To support an understanding of the concentration of TeF 6 contacting the adsorbent beds, a series of preliminary testing identified the TeF 6 production rate and the equilibrium concentration of TeF 6 in the gas stream contacting the adsorbent. Excess F 2 was determined to not affect the ability of activated alumina to remove TeF 6 from the gas stream quickly and completely. A determination of whether excess F 2 affected the distribution depth of Te in the sorbent bed is still pending analysis of the used sorbent. Literature suggests that when activated alumina is near saturation, TeF 6 could migrate from the sorbent bed. Future testing should investigate this possibility. Copper metal did not adsorb TeF 6 in the presence of F 2 across the sorbent temperature range of 50 to 335°C. F 2 was fully removed by the copper bed. Although preliminary thermodynamics would indicate adsorption to be energetically favorable, other factors that impact adsorption (e.g., slow kinetics, excess fluorine on the copper surface, an unfavorable transition state) are likely preventing the adsorption of TeF 6 at an easily measurable rate. The work also investigated TeF 6 production from multiple forms of Te in the temperature range of 100 to 250°C. No previous study had assessed the initial reaction rates for this process. A carefully designed study allowed determination of the activation energy for the production of TeF 6 from Te metal. The substantial amount of data collected during this study merits analysis beyond what is described here. A more in-depth kinetic analysis will be pursued. Additional analytical results will provide the ability to benchmark adsorption coefficients for TeF 6 , understand the distribution of TeF 6 within the alumina bed, and better understand the effect of F 2 partial pressure on Te fluorination. The data from this report, as supplemented by these additional analyses, will be submitted to a peer-reviewed journal.
The Los Alamos National Laboratory (LANL or the Laboratory) operates a Meteorological Monitoring (Met) Program to support LANL emergency response, engineering designs, environmental compliance, environmental assessments, safety evaluations, weather forecasting, environmental monitoring, research programs, and environmental restoration. Weather data has been collected in Los Alamos since 1910. A 30-year averaging period is termed by the National Weather Service (NWS) as a climatic normal, and these statistics are updated every 10 years to represent the current climatic normal conditions. Previous climate statistics are provided in Bowen (1990) for the 1961–1990 averaging period and Dewart et al. (2017) for the 1981–2010 averaging period. No climate statistics were developed for the 1971-2000 averaging period. This report provides climate statistics for the current 30-year 1991–2020 averaging period.