Kentucky Residential Energy Code Field Study: Baseline Report
This report summarizes the Phase I Residential Field Study results for Kentucky.
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This report summarizes the Phase I Residential Field Study results for Kentucky.
This report summarizes the initial results of the residential field study in the state of Maryland.
This report analyzes data from multi-arm caliper (MAC) surveys taken at the Big Hill SPR site to determine the most likely casing weights within each well. Radial arm data from MAC surveys were used to calculate the approximate wall thickness of each well. Results from this study indicate that (1) most wells at the site have thinner wall thicknesses than expected, (2) most wells experienced an acute increase in diameter near the salt/caprock interface, and (3) there were isolated instances of well sections being the wrong casing weight. All three findings could have a negative impact on well integrity.
The main goal of FY18 THM’s focus task is to evaluate where the current CASL boiling model stands for DNB predictive performance, to identify which components should be improved or calibrated to enhance DNB performance. Over the past three year’s validation tests, Gen1A boiling model has presented an under-predictive behavior for DNB at the high pressure of interest for PWR application. With this in mind, this year’s task is to focus on 1) best practice guidelines on DNB detection criteria, 2) interfacial momentum transfer closure tests, and 3) wall boiling closure sensitivity on DNB. Best practice guidelines on DNB detection criteria are demonstrated by the following three monitoring variables: 1) max wall temperature, 2) K-value and 3) energy balance. Interfacial momentum transfer closure govern the bubble distribution, especially in lateral direction, as well as bubble mean diameter. A clear correlation between interfacial momentum closure and DNB prediction is not observed in the current tests. However, void distributions are changed with different interfacial momentum closure tests which requires further validation with corresponding experimental measurement. From a variety of wall boiling closure tests, bubble departure diameter seems the most sensitive for DNB performance while fulfilling numerical robustness in DNB simulation. Tolubinski’s bubble departure diameter model was calibrated to see if any improvement is observed in DNB performance. Notable DNB improvement was observed as the bubble departure diameter is reduced. However, reduced bubble departure diameter by calibrated Tolubinski’s model seemed to lead to relatively high wall superheat temperature prediction which requires further validation with associated experimental measurement It should be noted that lack of experimental measurement close to DNB condition hampers this boiling closure sensitivity study significantly. This situation directly reflects some of limitations of the CASL boiling model development. With this in mind, the implementation of improved boiling closure on 5x5 NMVG and MVG tests will be pursued in FY19, the associated DNB best practice guidelines and possible limitations will be addressed for industry DNB application.
Neutron transport methods used to establish subcriticality require validation by comparison to critical experiments considered to be benchmarks. Whisper is a sensitivity/uncertainty analysis tool developed to assist with the task of validation in nuclear criticality safety.
This report presents the cost and performance results of pulverized coal (PC) and natural gas combined cycle (NGCC) plants, using a consistent technical and economic approach that reflects current market conditions. The primary value of this report lies not in the absolute accuracy of the capital cost estimates for the individual cases (estimated to be -15%/+30%), but in application of a consistent approach to allow meaningful comparisons of relative costs among the cases evaluated.
This report presents the cost and performance results of an assessment of seven integrated gasification combined cycle (IGCC) plants. The primary value of this report lies not in the absolute accuracy of the capital cost estimates for the individual cases (estimated to be -15 percent/+30), but in the application of a consistent approach to allow meaningful comparisons of relative costs among the cases evaluated.
A long term research focus of the US Department of Energy (DOE) Advanced Fuels Campaign (AFC) is to investigate technologies that can allow for increased actinide utilization in nuclear fuel for fast neutron spectrum reactors. This includes both the incorporation of minor actinides into nuclear fuel for transmutation and high utilization of actinides through “ultra high” burnup fuel. This goal is defined as fuel that can reach a burnup of 30-40 percent fission per initial metal atom (%FIMA) which is higher than what has historically been achieved [1],[2]. Historically, Experimental Breeder Reactor II (EBR-II) Mark III/IIIA/IV driver fuel (U 10Zr fuel with stainless steel 316 or ferritic martensitic steel HT-9 cladding) was qualified to 10%FIMA, but many experimental assemblies and fuel pins achieved higher peak burnup up to near 20%FIMA without failure [3]. The motivation of the irradiation tests explored in this work was to screen candidate alloys and forms that could tolerate very high burnup irradiations of up to 30 % FIMA. In these irradiations, termed AFC 3C, AFC-3D and AFC-4A, uranium-based alloys and forms were irradiated in a prototypic fast reactor spectrum to investigate fuel performance. Irradiations were performed in the Idaho National Laboratory (INL) Advanced Test Reactor (ATR). The performance of these fuels is compared to the historic performance of U-10Zr [4]. Metallic fuel for fast reactors has a long history that has been reviewed several time in the literature [3]–[8].
Previous NOvA talks considered neutral currents as a background to charged current processes. This talk discusses NOvA’s 2018 searches for neutral current disappearance, in which NCs are the signal!
This is an excerpt from INL/LTD-12-26154 that will be used to satisfy a deliverable for the Gen IV Sodium Fast Reactor Advanced Fuels Project Management Board.
This is an excerpt from INL/LTD-15-36358 that will be used to satisfy a deliverable for the Gen IV Sodium Fast Reactor Advanced Fuels Project Management Board.
This is an excerpt from INL/LTD-15-36358 that will be used to satisfy a deliverable for the Gen IV Sodium Fast Reactor Advanced Fuels Project Management Board.
This report establishes performance and cost data for coal-to-liquids systems, specifically by means of gasification and Fischer-Tropsch reaction. The analyses were performed on a consistent technical and economic basis to assess the design and financial performance of a commercial-scale coal-to-Fischer-Tropsch liquids facility. The cost and performance data were compiled from published reports, information obtained from vendor quotes and users of the technology, and data from designing and building utility and refining projects.
The proposed use of the subject property is for the purpose of adding a parking lot to serve the increase in customer vehicles that is occurring as the 9940 Main Complex is more heavily utilized, and as the 2009 Expansion areas come online as operational training facilities. The subject property would be used only for parking, not for testing or training activities. The parking lot would have a gravel surface. Current and future work at the 9940 Main Complex involves arming, fuzing, and firing of explosives and the testing of explosive systems components in both terrestrial and aquatic settings. It also involves specialized training activities for a variety of first responder customers, both DOE and non-DOE agencies.
This report presents an independent assessment of the cost and performance of select fossil energy power systems - integrated gasification combined cycle (IGCC), pulverized coal (PC), and natural gas combined cycle (NGCC) plants - using a systematic, transparent technical and economic approach.
Presented by NETL at GHGT-14, 10/18
Presented by NETL at EUEC 2019, 02/19
Gasification of coal, in addition to generating syngas for power production, has the potential to produce a diverse array of high-value products. It is a challenge to understand the optimal use of this domestic coal resource amidst the potential technology options, product slates (including co-production of power), and competing feedstocks (natural gas, petroleum). This analysis seeks to begin addressing that challenge by focusing on one primary product, methanol, which also serves as a readily-transportable intermediate to many other products including olefins, gasoline, and di-methyl ether (DME).