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At least 757 records · Page 42
All sourcesNASA NTRSDOE OSTI
DOE OSTI2018

Confirmatory LBL Analysis of AGR-5/6/7 Compacts and Over-Coated Particles BWXT Batches 11034, 14154C, 14156C, AND 14156D

Fuel for the Advanced Gas Reactor Fuel Development and Qualification (AGR) Program’s AGR-5/6/7 irradiation test in the Idaho National Laboratory (INL) Advanced Test Reactor (ATR) was produced by BWX Technologies (BWXT) Nuclear Operations Group in Lynchburg, Virginia. Tristructural isotropic (TRISO) coatings were deposited using a 150-mm-diameter production-scale fluidized-bed chemical vapor deposition (CVD) furnace on 425-μm-nominal-diameter spherical kernels from Lot J52R-16-69317 containing a mixture of 15.5% 235U low-enriched uranium carbide and uranium oxide (UCO). The TRISO coatings consisted of four consecutive CVD layers: a ~50% dense carbon buffer layer with 100-μmnominal thickness, a dense inner pyrolytic carbon (IPyC) layer with 40-μm-nominal thickness, a silicon carbide (SiC) layer with 35-μm-nominal thickness, and a dense outer pyrolytic carbon (OPyC) layer with 40-μm-nominal thickness. TRISO-coated particle Lot J52R-16-98005 was over-coated with a graphite/resin blend and these over-coated particles were pressed in half-inch-diameter, one-inch-long cylindrical compacts. Two packing fractions (PF) were produced, 40%PF and 25%PF, where the TRISO particle volume made up approximately 40% and 25% of the total compact volume, respectively. The AGR-5/6/7 Fuel Specification, SPC-1352 [Marshall 2016], provides the requirements necessary for acceptance of the fuel manufactured for the AGR-5/6/7 irradiation test. Quality control (QC) acceptance testing for all AGR-5/6/7 composited lots and single batches was performed by BWXT, with the exception of pyrolytic carbon (PyC) anisotropy and defective IPyC fraction in the TRISO candidate batches and final composite, which were measured at the Oak Ridge National Laboratory (ORNL) and reported in ORNL/TM-2017/036 [Hunn et al. 2017] and ORNL/TM-2017/037 [Helmreich et al. 2017a].

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2017

Alstom’s Chemical Looping Combustion Technology for CO 2 Capture for New and Retrofit Coal-Fired Power Plants

Cold Flow Modeling (CFM) is a critical tool to understand solid transport, corresponding process stability, and the impact on the performance of the LCL-CTM technology. As such it plays a central role in the development of the LCL-CTM process and deserves a standalone report in the final reporting on Phase II of the collaboration with DOE under award DE FE0009484. The 40-Foot Cold Flow Model (CFM) was constructed before the 3 MWth Prototype. The purpose of the CFM is to: develop design and operational information to design the Prototype help resolve solids transport problems that occur with the Prototype provide Prototype operator training. This report provides a review on the use of the CFM to achieve better understanding, design, and operation of solid transport for the LCL-CTM technology. Significant progress was made by iteratively designing, operating, and testing between the CFM and the Prototype scale. Fundamental understanding of the transport of reactive solids was acquired based on the reported effort. Unfortunately, the technical gaps identified for Phase II of the LCL-CTM technology development could not all be eliminated and the transport of solids under high fuel load remained unstable at the Prototype scale. The nature of the iterative learning going back and forth between CFM and Prototype scale became cost-prohibitive and forced the project to pivot at a relatively late date in the project. The LCL-CTM process switched from a Transport reactor design to a Bubbling Fluidized Bed (BFB) design in order to successfully achieve all process criteria but at the 100-kWth scale to accommodate the residual funding. The CFM remains a very relevant tool for future LCL-CTM process development. While the LCL-CTM technology still must be demonstrated under scale up conditions (and the success of the BFB testing would push to scale up in that configuration), the CFM will remain a preferred tool for troubleshooting and reducing the technical gaps of LCL-CTM.

01 COAL, LIGNITE, AND PEAT↗
DOE OSTI2017

Integrating Magnetotellurics, Soil Gas Geochemistry and Structural Analysis to Identify Hidden, High Enthalpy, Extensional Geothermal Systems

Our research group comprising personnel from University of Utah/EGI (UU/EGI), University of Nevada at Reno (UNR) and Lawrence Berkeley National Laboratory (LBNL) has been applying magnetotellurics (MT), diagnostic structural affiliations, and soil gas flux and geochemistry to assist in identifying hidden, high-enthalpy geothermal systems in extensional regimes of the U.S. Great Basin. We are specifically looking for upwelling low-resistivity and geologic structures that can carry fluids from magmatic or high-grade metamorphic conditions in the deep crust upward to exploitable depths, and to verify the nature of the deep sources through soil gas geochemical compositions. The project was motivated by prior MT transect coverage of western and central Nevada centered upon the Dixie Valley geothermal system where such favorable indicators were first recognized. The high-angle structures are taken to be fluidized fault zones connecting deep magmatic/metamorphic activity with the geothermal system but the concept requires verification by testing at other systems. The project was set up with a two-phased organization. Phase I was carried out at the McGinness Hills system, central Nevada, where Ormat’s flagship power facility is located and a considerable amount of pre-existing data was available. Transect MT data also showed a strong low-resistivity upwelling originating from interpreted deep crustal magmatic underplating. Controlling structures on production as indicated by Ormat data and new mapping by UNR were favorable to dilatency being an accommodation zone between major normal faults of opposing dip. A 3D MT survey and inversion confirmed the existence of the steep low-resistivity zone dipping ESE toward the deep crust and placed N-S bounds upon the feature. Ormat personnel cooperated with PI Wannamaker in the field in providing fluid samples from the production intervals for He isotope composition. Elevated 3He was verified through analysis at LBNL confirming that there was a magmatic connection into the producing system. High CO2 soil gas flux including possibly metamorphic 13C and 14C component was measured over the area of dilatent structures. Hence, the triad of indicators posed above was confirmed in Phase I. Subsequently, Phase II of the project proceeded in the greenfield Kumiva-Blackrock Desert district of northwestern Nevada to see if a new system could be identified. Transect MT data also showed a strong low-resistivity upwelling originating from interpreted deep crustal magmatic underplating. However, given that there was no exploitable geothermal system recognized at the outset in the region, the collection of new geoscientific data was required. An areal MT survey of 131 sites over the Kumiva-Blackrock Desert district was completed, and a 3D inversion produced using the in-house, DOE-supported finite element inversion algorithm. Particular MT low resistivity upwellings that received followup study occurred under the west flank of the Seven Troughs Range, under the playa immediately west of the Blue Wing Mountains, and under northern Granite Springs Valley. Structural assessment of the project area by Co-I J. Faulds at UNR provided numerous favorable Quaternary fault settings, which were correlated to the MT upwelling structures. Extensive profiling for CO2 soil gas flux over favorable geophysical and geological structure was performed by LBNL personnel. Soil gas flux anomalies generally were not large but did show correlation with MT upwelling structure and favorably dilatent geological structures. Isotope analyses showed presence of possible inorganic/metamorphic 13C but 14C concentrations did not exceed background values. We view the initial concept of a confluence of MT low-resistivity upwelling, favorably dilatent 3D geological structure, and elevated soil gas flux including 13C component to be supported by the further evidence of this project although the indicators in the Phase II study were more diffuse. The northern Granite Springs Valley structure is receiving followup in the UNR Play Fairway Analysis, being in the southern termination of a major normal fault with silicified soil and warm temperature probe results

15 GEOTHERMAL ENERGY↗
DOE OSTI2018

FY18Q2 Quarterly Report: Radiation Enhanced Diffusion of Ag, Ag-Pd, Eu, and Sr in Neutron Irradiated PyC/SiC Diffusion Couples

Obtaining accurate diffusion kinetics in materials representative of those found in tristructural-isotopic (TRISO) coated particle fuel is needed to predict the diffusive release of fission products in reactor. Planar diffusion couples with representative pyrocarbon (PyC) and silicon carbide (SiC) layers are being produced using the same fluidized-bed chemical vapor deposition (FBCVD) technology used to produce TRISO particles from the first irradiation experiment of the Advanced Gas Reactor (AGR) Fuel Qualification and Development Program. The layer properties of the planar diffusion couples are tailored to meet the specified PyC density and microstructure of the SiC layer as defined by the AGR program. The influence of these variables on diffusion is also being explored by producing PyC and SiC variants.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

FY18Q1 Quarterly Report: Radiation Enhanced Diffusion of Ag, Ag-Pd, Eu, and Sr in Neutron Irradiated PyC/SiC Diffusion Couples

Obtaining accurate diffusion kinetics in materials representative of those found in tristructural-isotopic (TRISO) coated particle fuel is needed to predict the diffusive release of the same fission products in reactor. Planar diffusion couples with representative pyrocarbon (PyC) and silicon carbide (SiC) layers are being produced using the same fluidized-bed chemical vapor deposition (FB-CVD) technology used to produce TRISO particles from the first irradiation experiment of the Advanced Gas Reactor Fuel Qualification and Development Program (AGR). The layer properties of the planar diffusion couples are tailored to meet the specified PyC density and microstructure of the SiC layer as defined by the AGR program. The influence of these variables on diffusion is also being explored by producing PyC and SiC variants. The pathway to producing the diffusion couples is discussed.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

Chemics-Reactors: A Preliminary Python Program for Implementing Network Models of Multiphase Reactors

We discuss the design and implementation of a preliminary software package written in Python 3 that is intended to represent complex multiphase reactors as networks of ideal continuous stirred tank reactors. This software also implements statistical design of experiments, uncertainty quantification, and global sensitivity analysis. These advanced features can provide important qualitative and quantitative insights into the effect of operating conditions and model parameters on predicted reactor performance. We demonstrate the utility of the program by modeling the vapor phase catalytic upgrading of bio-oil in a bubbling fluidized bed reactor.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2018

FY18Q3 Quarterly Report: Radiation Enhanced Diffusion of Ag, Ag-Pd, Eu, and Sr in Neutron Irradiated PyC/SiC Diffusion Couples

Obtaining accurate diffusion kinetics in materials representative of those found in tristructural-isotopic (TRISO) coated particle fuel is needed to predict the diffusive release of fission products in reactor. Planar diffusion couples with representative pyrocarbon (PyC) and silicon carbide (SiC) layers are being produced using the same fluidized-bed chemical vapor deposition (FBCVD) technology used to produce TRISO particles from the first irradiation experiment of the Advanced Gas Reactor (AGR) Fuel Qualification and Development Program. The layer properties of the planar diffusion couples are tailored to meet the specified PyC density and microstructure of the SiC layer as defined by the AGR program. The influence of these variables on diffusion is also being explored by producing PyC and SiC variants. The pathway to producing the diffusion couples is discussed and builds upon efforts described in previous reports [1–3].

36 MATERIALS SCIENCE↗
DOE OSTI2018

Validation and optimization of batch and continuous particle separation processes

Recent advances in simulation capabilities coupled with advanced manufacturing can be leveraged to create highly efficient compact reactors with low emissions, low cost, high reliability, and high flexibility for energy conversion. This type of reactor is especially important for conversion of bio-mass, a storable, renewable and fast-growing energy source, considering the distributed nature of raw material and cost of biomass collection and transportation. To achieve this goal, it is critical to developing new process technologies that are significantly more efficient than traditional processes for which the added manufacture provides a fast way of realization and evaluation. Based upon the flagship MFiX multiphase computational fluid dynamic software suite, NETL has developed an Optimization Toolset to facilitate the CFD simulation based reactor design and optimization, and process intensification. This technical report presents the recent development and application of the Optimization Toolset and the framework for process optimization of particle separation in batch and continuous processes. In these processes, a fluidized bed reactor under proper operating condition was used to separate particles of different physical properties. MFiX-DEM simulations were conducted for a batch system to simulate the process covering a wide range of superficial gas velocities from which the optimal operational parameter can be determined through analyzing the system response. After successful demonstration of the framework, a continuous system for particle separation was designed based on CFD simulations. Similar optimization exercises were conducted for the continuous particle separation considering multiple operating parameters. The design was then fabricated in the laboratory through 3D printing for testing. The particle separation performance was carefully measured through high-speed video for particle tracking. Quantitative comparison between numerical results and experimental measurements were conducted for confirmation and validation.

30 DIRECT ENERGY CONVERSION↗
DOE OSTI2018

Biological System Characterization to Address Biofouling of the 200 West Pump-and-Treat Injection Wells

Contaminated groundwater in the 200W Area of the Hanford Site is being treated ex situ by the 200W Pump-and-Treat (P&T) Facility and the subsurface plume is under hydraulic containment. The 200W P&T Facility removes several contaminants of concern from groundwater, as well as nitrate. Facility capacity is constrained by biofouling of injection wells, which limits the ability to efficiently inject treated effluent water in to the subsurface. In a previous report, Thomle et al. provided a comprehensive engineering assessment of biofouling at the 200W P&T Facility. In that report, both operational changes and facility modifications were recommended to help mitigate the symptoms and consequences of biofouling by expanding treatment processes in the plant. The 200W P&T Facility’s fluidized bed reactor (FBR) is a biological treatment system that has been identified as a principal source of biofouling. Carbon and nutrient inputs to the FBR are needed to sustain high rates of activity, but can also be responsible for microbial proliferation in the effluent water distribution pipeline, and loss injection well capacity. The primary objective of this work was to fill critical knowledge gaps associated with the FBR that can be used to optimize the biological system for continuous operation and sustained performance.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2017

Techno-economic Evaluation of Utility-Scale Power Plants Based on the Indirect sCO 2 Brayton Cycle - Report

This report presents the results of a techno-economic analysis (TEA) of a coal-fired utility scale power plant based on the indirect supercritical carbon dioxide (sCO 2 ) Brayton cycle using an oxy-fired circulating fluidized bed (CFB). A baseline plant configuration was examined as well as three variations to the sCO 2 power cycle examining the impact of reheat (Rht), main compressor intercooling (IC), and a combination of reheat and main compressor intercooling (RhtIC). Each plant configuration was assessed at two turbine inlet temperatures of 620 °C and 760 °C.

20 FOSSIL-FUELED POWER PLANTS↗
DOE OSTI2017

Techno-economic Evaluation of Utility-Scale Power Plants Based on the Indirect sCO2 Brayton Cycle - Presentation

This presentation discusses the results of a techno-economic analysis (TEA) of a coal-fired utility scale power plant based on the indirect supercritical carbon dioxide (sCO2) Brayton cycle using an oxy-fired circulating fluidized bed (CFB). A baseline plant configuration was examined as well as three variations to the sCO2 power cycle examining the impact of reheat (Rht), main compressor intercooling (IC), and a combination of reheat and main compressor intercooling (RhtIC). Each plant configuration was assessed at two turbine inlet temperatures of 620 °C and 760 °C.

Brayton power cycle↗
DOE OSTI2018

User Guide for the Public Industrial CO 2 Capture Retrofit Database Models

The United States (U.S.) Department of Energy’s (DOE) National Energy Technology Laboratory (NETL) has produced three carbon capture retrofit databases (CCRDs), which contain a collection of units selected from the power generation and industrial sources (IND) sectors located in the United States that are either in operating or standby status. The power generation category is subdivided into the post-combustion (PC) CCRD – containing coal-fired and atmospheric fluidized bed (AFB) units – and the natural gas combined cycle (NGCC) CCRD – containing natural gas-fired combined cycle and combined cycle single shaft units. The IND CCRD contains facilities from the ammonia, cement, ethanol, hydrogen, and natural gas processing industries. This report is intended to provide a general guide to the IND CCRD. Efforts have been made to ensure similarities between each of the CCRDs. However, as the sources of CO2 vary, differences will exist – most notably in the IND CCRD.

03 NATURAL GAS↗
DOE OSTI2018

User Guide for the Public PC and NGCC CO 2 Capture Retrofit Database Models

The United States (U.S.) Department of Energy’s (DOE) National Energy Technology Laboratory (NETL) has produced three carbon capture retrofit databases (CCRDs), which contain a collection of units selected from the power generation and industrial sources (IND) sectors located in the United States that are either in operating or standby status. The power generation category is subdivided into the post-combustion (PC) CCRD – containing coal-fired and atmospheric fluidized bed (AFB) units – and the natural gas combined cycle (NGCC) CCRD – containing natural gas-fired combined cycle and combined cycle single shaft units. The IND CCRD contains facilities from the ammonia, cement, ethanol, hydrogen, and natural gas processing industries. Public versions of these databases were created for use by individuals interested in exploring the impact of retrofitting plants with carbon capture. The power versions contain data from the NETL baseline reports as examples of information that a user can enter for plants of interest. This report is intended to provide a general guide to each of the power CCRDs. Efforts have been made to ensure similarities between each of the CCRDs. However, as the sources of CO 2 vary, differences will exist – most notably in the IND CCRD. Therefore, the PC and NGCC CCRDs are discussed in this guide.

20 FOSSIL-FUELED POWER PLANTS↗
DOE OSTI2019

Dover Light & Power 10 MWe Coal Direct Chemical Looping (CDCL) (Large Pilot Plant Test - Phase I Feasibility)

A feasibility study was conducted to install a 10 MWe coal direct chemical looping large pilot plant at a host site. The coal direct chemical looping technology was based on The Ohio State University and Babcock & Wilcox iron-based metal oxide technology coupling a moving bed reduction reactor with a circulating fluidized-bed oxidation reactor. The host site was the Dover Light & power Plant in Dover, Ohio. The Electric Power Research Institute performed the host site evaluation. Trinity Consultants prepared the Environmental Information Volume. WorleyParsons Group performed the civil engineering. Clear Skies Consulting served as lead on the Industrial Advisory Committee.

20 FOSSIL-FUELED POWER PLANTS↗
DOE OSTI2019

Additional Confirmatory LBL Analysis of AGR-5/6/7 Compacts and Over-Coated Particles

Fuel compacts for the Advanced Gas Reactor Fuel Development and Qualification (AGR) Program’s AGR-5/6/7 irradiation test in the Idaho National Laboratory (INL) Advanced Test Reactor (ATR) were fabricated by BWX Technologies Nuclear Operations Group (BWXT NOG) located in Lynchburg, Virginia. Two compact packing fractions (PFs) were produced - nominally, 40% PF and 25% PF - in which the tristructural-isotropic (TRISO)-coated particle volume was targeted to be approximately 40% and 25% of the total compact volume, respectively. The TRISO coatings were deposited using a 150 mm diameter fluidized-bed chemical vapor deposition (CVD) furnace on spherical kernels that were nominally 425 μm in diameter. The kernels were from kernel composite Lot J52R-16-69317, which contained low-enriched uranium (15.5% 235 U) in a mixture of uranium carbide and uranium oxide (UCO). Kernels were coated with four concentric CVD layers: a porous carbon buffer layer that was nominally 100 μm thick, an inner pyrolytic carbon (IPyC) layer that was nominally 40 μm thick, a silicon carbide (SiC) layer that was nominally 35 μm thick, and an outer pyrolytic carbon (OPyC) layer that was nominally 40-μm-thick. Coated particle composite J52R-16-98005 was overcoated (OC) with a graphite/resin blend, and these OC TRISO particles were pressed to form cylindrical compacts that were nominally a half inch in diameter and one inch long.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2017

Moving Bed Chemical Looping Combustion Fuel Reactor Modeling and Sensitivity Analysis

Chemical looping combustion (CLC) is a novel, coal-based power generation technology that has currently achieved only small-scale, non-integrated development status, with the fuel reactor being the key developmental component in the CLC process. Both circulating fluidized bed (CFB) and moving bed fuel reactors have been the subjects of ongoing development campaigns. The objective of the effort described in this report is to characterize a moving bed fuel reactor by applying more detailed, reaction kinetics-based models that represent the nature of this reactor with a more fundamental foundation than has previously been reported by developers. This report describes the modeling basis, and a “base” fuel reactor’s design and performance characteristics resulting from the model. A major focus of the evaluation has been placed on studies of the sensitivity of the base moving bed fuel reactor performance, design, and CLC power plant cost implications to the key parameters.

20 FOSSIL-FUELED POWER PLANTS↗
DOE OSTI2020

Destructive PIE and Safety Testing of Six AGR-2 UO 2 Capsule 3 Compacts

The Advanced Gas Reactor (AGR) Fuel Development and Qualification Program’s second irradiation experiment (AGR-2) was irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) from June 2010 to October 2013 (Collin 2014). The fuel compacts in this experiment held either tristructural isotropic (TRISO)-coated spherical kernels of uranium oxide (UO2) or TRISO-coated kernels containing both uranium carbide and uranium oxide phases (UCO). There were six separately monitored and controlled capsules in the AGR-2 test train. Capsule 3 held twelve compacts containing UO2-TRISO particles fabricated by BWX Technologies Nuclear Operations Group. The AGR-2 TRISO particles were fabricated in a pilot-scale fluidized-bed chemical vapor deposition (FB-CVD) furnace with a coating chamber inner diameter of 150 mm (Phillips, Barnes, and Hunn 2010), which was a change from the first irradiation experiment (AGR-1) particles that had been coated in a lab-scale FB-CVD coating system with a chamber inner diameter of 50 mm (Lowden 2006). The TRISO particles were overcoated with resinated graphite flake at Oak Ridge National Laboratory (ORNL), and the overcoated particles were pressed into one-inch-long, half-inch-diameter cylinders (Hunn, Montgomery, and Pappano 2010). Each cylindrical compact held an average of 1,543 TRISO particles with 9.6% enriched UO2 kernels that had a nominal diameter of 500 μm (Hunn, Savage, and Silva 2012). Capsule 3 compacts were irradiated to average calculated burnups of 9.01–10.69% fissions per initial metal atom (FIMA), and the average calculated fluences of fast neutrons with energies E n > 0.18 MeV were 3.05–3.53×10 25 n/m 2 (Sterbentz 2014). The calculated time-average, volume-average Capsule 3 compact temperatures were 996–1,062°C. However, Capsule 3 compact temperatures varied several hundred degrees across each compact, and the timeaverage minimum (TA min ) and time-average maximum (TA max ) temperatures were between 889–999°C and 1,072–1,105°C, respectively (Hawkes 2014). After irradiation, the AGR-2 test train was transferred from ATR to the INL Materials and Fuels Complex for inspection and disassembly (Ploger, Demkowicz, and Harp 2015). The initial inspection included dimensional metrology of the compacts and graphite fuel holders. Like all the AGR-2 compacts, the compacts in Capsule 3 shrank slightly during irradiation, as expected, with an average length reduction of 1.07–1.24% and an average diameter reduction of 0.13–0.41%. Post-irradiation examination (PIE) of the capsule components was completed to measure select fission products ( 90 Sr, 110m Ag, 134 Cs, 137 Cs, 144 Ce, and 154 Eu) outside the compacts (Stempien and Demkowicz 2020). This involved gamma counting of the graphite and graphoil spacers at the top and bottom of each capsule, acid leaching for radiochemical analysis of fission products on the metallic capsule components, and burn-leach analysis of the graphite holders. The total amount of 110mAg measured on the Capsule 3 components was 13% of the calculated capsule inventory. This was significantly lower than the amount of 110m Ag measured on the three UCO capsule components, which ranged from 32–70%. The lower 110m Ag release in Capsule 3 was likely due to lower peak temperatures compared with the UCO fuel capsules (Hawkes 2014). Measured inventories of the other select fission products were also lower in Capsule 3.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗