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At least 991 records · Page 55

TOGA: A TOUGH code for modeling three-phase, multi-component, and non-isothermal processes involved in CO 2 -based Enhanced Oil Recovery

TOGA is a numerical reservoir simulator for modeling non-isothermal flow and transport of water, CO 2 , multicomponent oil, and related gas components for applications including CO 2 -enhanced oil recovery (CO 2 -EOR) and geologic carbon sequestration in depleted oil and gas reservoirs. TOGA uses an approach based on the Peng-Robinson equation of state (PR-EOS) to calculate the thermophysical properties of the gas and oil phases including the gas/oil components dissolved in the aqueous phase, and uses a mixing model to estimate the thermophysical properties of the aqueous phase. The phase behavior (e.g., occurrence and disappearance of the three phases, gas + oil + aqueous) and the partitioning of non-aqueous components (e.g., CO 2 , CH 4 , and n-oil components) between coexisting phases are modeled using K-values derived from assumptions of equal-fugacity that have been demonstrated to be very accurate as shown by comparison to measured data. Models for saturated (water) vapor pressure and water solubility (in the oil phase) are used to calculate the partitioning of the water (H 2 O) component between the gas and oil phases. All components (e.g., CO 2 , H 2 O, and n hydrocarbon components) are allowed to be present in all phases (aqueous, gaseous, and oil). TOGA uses a multiphase version of Darcy’s Law to model flow and transport through porous media of mixtures with up to three phases over a range of pressures and temperatures appropriate to hydrocarbon recovery and geologic carbon sequestration systems. Transport of the gaseous and dissolved components is by advection and Fickian molecular diffusion. New methods for phase partitioning and thermophysical property modeling in TOGA have been validated against experimental data published in the literature for describing phase partitioning and phase behavior. Flow and transport has been verified by testing against related TOUGH2 EOS modules and CMG. The code has also been validated against a CO 2 -EOR experimental core flood involving flow of three phases and 12 components. Results of simulations of a hypothetical 3D CO 2 -EOR problem involving three phases and multiple components are presented to demonstrate the field-scale capabilities of the new code. This user guide provides instructions for use and sample problems for verification and demonstration.

97 MATHEMATICS AND COMPUTING↗

The Effect of Rolling As-Cast and Homogenized U-10Mo Samples on the Microstructure Development and Recovery Curves

Over the past several years Pacific Northwest National Laboratory (PNNL) has been actively involved in supporting the U.S. Department of Energy National Nuclear Security Administration Office of Material Management and Minimization (formerly Global Threat Reduction Initiative). The U.S. High- Power Research Reactor (USHPRR) project is developing alternatives to existing highly enriched uranium alloy fuel to reduce the proliferation threat. One option for a high-density metal fuel is uranium alloyed with 10 wt% molybdenum (U-10Mo). Forming the U-10Mo fuel plates/foils via rolling is an effective technique and is actively being pursued as part of the baseline manufacturing process. The processing of these fuel plates requires systematic investigation/understanding of the pre- and post-rolling microstructure, end-state mechanical properties, residual stresses, and defects, their effect on the mill during processing, and eventually, their in-reactor performance. In the work documented herein, studies were conducted to determine the effect of cold and hot rolling the as-cast and homogenized U-10Mo on its microstructure and hardness. The samples were homogenized at 900°C for 48 h, then later annealed for several durations and temperatures to investigate the effect on the material’s microstructure and hardness. The rolling of the as-cast plate, both hot and cold, was observed to form a molybdenum-rich and -lean banded structure. The cold rolling was ineffective, and in some cases exacerbated the as-cast defects. The grains elongated along the rolling direction and formed a pancake shape, while the carbides fractured perpendicularly to the rolling direction and left porosity between fractured particles of UC. The subsequent annealing of these samples at sub-eutectoid temperatures led to rapid precipitation of the ' lamellar phase, mainly in the molybdenum-lean regions. Annealing the samples above the eutectoid temperature did not refine the grain size or the banded microstructure. However, annealing the samples led to quick recovery in hardness as evidenced by a drop in Vickers hardness of 20%. Hot rolling was performed at 650 and 800°C. The hot-rolling mill loads (load separation force) were approximately 40 to 50% less than the cold-rolling for the same reduction and thickness. It was observed that hot rolling the samples with 50% or more reduction in thickness were responsible for dynamic recrystallization in the hot-rolled samples and led to grain refinement. Unlike the cold-rolled samples, the hot-rolled samples did not fracture the carbides and appeared to heal the casting defects. The recovery phenomenon was similar to the cold-rolled samples above the eutectoid temperatures, but owing to the refined grain size, the precipitation of the lamellar phase was far more rapid in these samples and the hardness increased more rapidly than in the cold rolled sample when heated below the eutectoid temperature. The data generated from these rolling efforts has been used to make the process modeling efforts more robust and applicable to all USHPRR partner rolling mills. The flow stress for cold rolling the samples was determined to be between 170-190 ksi, with frictional forces between 0.2 and 0.4 for the PNNL mill. The measured roll separation forces and those simulated using finite element methods for hot and cold rolling for the PNNL rolling mill were in good agreement.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Hydraulic Testing of Lost Lake Aquifer Near Recovery Wells RWM018, RWM 3, and RWM 5

An aquifer pumping test was conducted on the Lost Lake Aquifer Zone (LLAZ) at the recently installed recovery well RWM018 in accordance with the approved test plan (Dixon, 2018). The objective of the testing was to determine baseline well performance parameters and aquifer hydraulic conductivity. Well performance parameters determined included specific capacity, well efficiency, and head loss coefficients. The specific capacity of RWM018 was determined to be approximately 3.2 gpm/ft of drawdown. At baseline conditions (all active recovery wells operating except RWM018), RWM018 has approximately 26 ft of head above the well screen. This suggests that RWM018 can sustain a maximum pumping rate of 83 gpm with drawdown at the top of screen. Well efficiency was inversely related to pumping rate and decreased from 97% to 91% over a pumping range of approximately 20 to 55 gpm. These results suggest that RWM018 is an efficient well and does not require any further well development activities. The aquifer head loss coefficient was determined to be 2.1 ft/ft 3 /min and the well loss coefficient was determined to be 0.03 min 2 /ft 5 .

42 ENGINEERING↗

Hydraulic Testing of Lost Lake Aquifer Near Recovery Wells RWM018, RWM 3, and RWM 5

An aquifer pumping test was conducted on the Lost Lake Aquifer Zone (LLAZ) at the recently installed recovery well RWM018 in accordance with the approved test plan (Dixon, 2018). The objective of the testing was to determine baseline well performance parameters and aquifer hydraulic conductivity. Well performance parameters determine d included specific capacity, well efficiency, and head loss coefficients. The specific capacity of RWM018 was determined to be approximately 3.2 gpm/ft of drawdown. At baseline conditions (all active recovery wells operating except RWM018), RWM018 has approximately 26 ft of head above the well screen. This suggests that RWM018 can sustain a maximum pumping rate of 83 gpm with drawdown at the top of screen. Well efficiency was inversely related to pumping rate and decreased from 97% to 91% over a pumping range of approximately 20 to 55 gpm. These results suggest that RWM018 is an efficient well and does not require any further well development activities. The aquifer head loss coefficient was determined to be 2.1 ft/ft 3 /min and the well loss coefficient was determined to be 0.03 min 2 /ft 5 .

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗

Initial performance of the magnet system in the splitter/combiner section of the Cornell-Brookhaven Energy-Recovery Linac Test Accelerator

The Cornell-Brookhaven Energy-recovery Linac Test Ac- celerator is a four-pass, 150-MeV electron accelerator with a six-cell 1.3 GHz superconducting-RF linear accelerator and a fixed-field alternating-gradient (FFAG) return loop made up of Halbach-style quadrupole magnets. The optics matching between the linear accelerator and the return loop is achieved with a conventional magnet system comprised of 50 dipole magnets and 64 quadrupole magnets in four beamlines at each end of the linac. The 42-, 78-, 114- and 150-MeV electron beams are separated into independent vacuum chambers in order to allow for the path-length ad- justment required by energy recovery. We report on the first beam tests of the initial installation of the splitter/combiner section at the exit of the linac. The vacuum system of the 42-MeV S1 line was installed during the first week of April. Nine dipole and four quadrupole magnets were installed and surveyed into position the following week, and the water cooling system was commissioned. A 6-MeV beam passed through the line on April 11 with no need for adjusting pre-set magnet excitation currents. One week later, time- of-flight measurements were used to calibrate and phase the individual superconducting RF cavities. The S1 magnet settings were then scaled up to achieve 5-cavity, 42-MeV operation through the first nine FFAG permanent-magnet quadrupoles. This initial Fractional Arc Test will conclude on May 18, when the installation of the remaining seven split- ter/combiner lines and the return loop will begin. CBETA operations are scheduled to begin in early 2019.

43 PARTICLE ACCELERATORS↗

Gate-to-Gate Life Cycle Analysis Model of Enhanced Oil Recovery [Slides]

A gate-to-gate life cycle analysis (LCA) model was created to quantify the environmental impacts of the various processes associated with enhanced oil recovery (EOR). The following unit processes are accounted for in this analysis: injection and recovery, bulk separation and storage, gas separation, supporting processes, and land use. This analysis used an LCA approach for developing data and EOR and gas processing. The energy and material flows for key processes within the gate-to-gate boundaries of the EOR site were calculated. These processes were then compiled in a model that scaled the flows between processes to arrive at an inventory of environmental burdens on a common basis (e.g., 1 barrel of crude produced via EOR).

02 PETROLEUM↗

Subject Matter Expert Workshop for the Use of Municipal and Commercial Equipment for Radiological Response and Recovery: Argonne National Laboratory Workshop Summary Report

This report summarizes a workshop held in Argonne National Laboratory to identify the equipment and databases that support methods that might be available for emergency operations. Specifically, the Environmental Protection Agency and the Department of Homeland Security identified a need to develop response and recovery guidance to mitigate the effects of a radiological or nuclear release that compromises recovery in an urban environment or at a critical infrastructure. The objective of this workshop was to discuss the experience of the first responder community and environmental remediation specialists to identify equipment and methods that may be used to accomplish various missions summarized under five broad support goals. This document summarizes the comments from the Argonne National Laboratory meeting. Based on the findings and input from a series of such workshops, we plan to develop “best practices” for use of equipment responding to and recovering from a wide-area radiological incident.

63 RADIATION, THERMAL, AND OTHER ENVIRON. POLLUTAN↗

Sparse Recovery for Scientific Data

We have built build and analyzed fundamental mathematical tools that enable sparse recovery of scientific data for high performance computing, experimental facilities and sensor measurement. The proposed work will impact many areas of research across the DOE. We have designed, developed and analyzed fast scalable algorithms for the sparse recovery of scientific data sets that may be extremely large, generated very quickly and distributed across multiple storage devices. The algorithms we developed will be used to process the copious amounts of scientific data generated by the DOE supercomputer simulations and by DOE experimental and observational facilities. They leverage the fact that while the amount of data produced can be extremely large, the actual quantities of interest (QoI's) are often sparse, either in space time, or in some feature space. Mathematically, notions of compressive sensing, including l1 regularized and total variation regularized optimization have played an important part in this effort.

97 MATHEMATICS AND COMPUTING↗

Developing a Recovery Column for Mo-99 from Highly Concentrated Uranyl Nitrate Solutions

The feasibility of a highly concentrated uranyl nitrate target for 99 Mo production and recovery was investigated with respect to three separate resins. Two resins were inorganic-based – titania and zirconia – and the other was organic-based utilizing Aliquot® 336 extraction chromatography. Results show that pH has a significant effect on select fission products such as Zr whereas Mo is reasonably well retained between pH 0 and 2. Temperature also appreciably affected the retention of Mo. Using a normal-phase titania resin (Sachtapore®), the sorption of Mo was investigated by varying acid and uranium concentrations. The stability of the resin was also studied as a function of acid concentration. Results from the batch studies were then input into the in-house Versatile Reaction Separation (VERSE) code in order to design and optimize a recovery column for 99 Mo. The experimental and model results show that >99.9% of the 99 Mo can be recovered in the presence of saturated uranyl nitrate solutions.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Economic Extraction and Recovery of REEs and Production of Clean Value-Added Products from Low-Rank Coal Fly Ash

The University of North Dakota (UND) Energy & Environmental Research Center (EERC) teamed with Pacific Northwest National Laboratory (PNNL) , the North Dakota Industrial Commission Lignite Research Program, and commercial partners Basin Electric Power Cooperative, Great River Energy, and Southern Company to execute a Cooperative Agreement funded by the U.S. Department of Energy’s (DOE’s) National Energy Technology Laboratory (NETL) focused on identifying unique pathways and pretreatments to extract rare-earth elements (REEs) from low-rank coal (LRC) ash in a more economical and environmentally benign manner than current methods. The EERC drew upon the unique and deep knowledge of the team regarding LRC geochemistry, ash transformation mechanisms during combustion, and fly ash chemistry in the approach to understand the portioning of REEs in LRC ash. A comprehensive characterization effort was undertaken to fully establish the form, associations, and partitioning of the REEs and other elements/minerals of interest in fly ash, as well as the ash chemistry, mineralogy, and morphology. Using this information, the team tested methods of REE extraction to take advantage of the unique and advantageous properties of LRC ash. Multiple complementary approaches were evaluated that combined both novel and proven methods to develop an extractive process for REEs and other high-value metals from LRC ash that provide technological and economic progress on the current state of the art. Methodologies were also evaluated for the potential to synergistically remove toxic metals while extracting other high-value metals from the ash, generating a clean, safe ash material as a value-added product. This would eliminate waste and offer significant additional revenue potential. Based on laboratory-scale testing, an initial high-level technical and economic analysis to estimate operating expenses and product revenues to guide future phases of technology development was implemented. By focusing on minimizing process steps and consumptive use of extraction solutions, a tunable, economically viable process for REE extraction from LRC ash was developed. The tunable process has the ability to be adjusted to adapt to the differing ash chemical and physical properties that are characteristic of LRC ash. This is key to deployment as a commercial process. In demonstrating the process, the EERC was able to illustrate mixed REE concentration greater than the goal of 2 wt%. High-level economic analysis of the process with LRC ash of moderate REE levels demonstrated the potential of the process, but recovery of just the REEs was insufficient to cover operational costs. With the additional extraction of other high-value metals found in LRC ash, the process economics approach would break even, and it is anticipated that with process optimization, the developed process could potentially be economically sound. The same economic analysis performed utilizing LRC ash with high levels of REEs showed the recovery of the REEs alone would make the process economically viable even without further optimization.

01 COAL, LIGNITE, AND PEAT↗

Efficient Isotope Recovery and Seamless Recycle of Target Material in a Salt Matrix

A first step in developing molten salt nuclear reactors (MSRs) is a capability to irradiate capsules containing molten salts and a natural development path for this capability is through applications to produce radioisotopes using a molten salt matrix within existing water-cooled reactors. At present there is almost no capability to prepare, irradiate, and process salts for isotope production in the United States. This report documents an initial plan to discover designs for capsules to produce various radioisotopes ( 99 Mo, 238 Pu, 232 U, and heavy elements) in a way that minimizes waste, simplifies (or really eliminates the need for) recycle/refabrication operations by utilizing a salt matrix for irradiation and nonaqueous, aqueous, or hybrid processes for recovery of the isotopes from the salt matrix. The FY19 goals of this internal study are to: (1) Review past and current salt irradiation vehicle designs and evaluate modern materials, fabrication methods, and design methods to see how new vehicles could function for isotope production in the context of optimized nonaqueous or hybrid recovery methods.(2) engage potential end-users with this approach and gather feedback and provide recommendations for a phased implementation for different application/isotope domains. Oak Ridge National Laboratory (ORNL) staff have developed a unique understanding and capability with regard to molten salts and related pyro-processing methods. This capability can be sustained by passing it on to a new generation by tackling a challenging problem and putting the solution into practice. This study defines opportunities to start down that path.

07 ISOTOPE AND RADIATION SOURCES↗

Chemical Processes for Recovery of High Purity 234 U from Aged 238 PU

Purified 234 U (2.46E5 a) is an important radioisotope for commercial customers, and since the 1980s, the United States has experienced a market demand of 2–6 g per year. Purified 234 U is most efficiently recovered as a decay daughter from aged 238 Pu (87.7 a). Ever since the last recovery of tens of grams of 234 U by Monsanto Co.’s Mound Laboratory in 1980s, the DOE inventory of 234 U for US market decreased steadily. In 2016–2018, the Radiochemical Engineering Development Center at Oak Ridge National Laboratory (ORNL) carried out a campaign to recover 234 U from 16 spent Pu–Be neutron sources. A total 66.5 g of high purity 234 U of high isotopic abundance (>99.3%) was recovered in two phases of the campaign with selected chemical processes. Recovery of 234 U from aged 238 Pu commonly involves four major steps: (1) bulk plutonium removal from the matrix, (2) continued separation of plutonium from the matrix, (3) purification of 234 U from all other impurities, and (4) conversion of purified 234 U into a final product form, 234 U 3 O 8 . The first three steps are the key to ensuring the purity of the 234 U product. Historically, various chemical processes have been applied for uranium processing of these three steps, although on different scales or with different purity requirements. Because of the higher purity requirements specified for this order of 234 U product, the selected processing methods used in this campaign relied on a cyclical anion exchange process with MP-1 resins followed by uranium peroxide process to achieve the purified product. Process details will be compared with other options, and advantages and drawbacks will also be discussed.

07 ISOTOPE AND RADIATION SOURCES↗

Recovery of High Purity Rare Earth Elements (REE) from Coal Ash via a Novel Electrowinning Process (Final Report)

The goal of this project was to produce a high purity, separated (>90%) rare earth oxide (REO) product from coal-based sources. This product was achieved using the following three steps: 1. Battelle’s ADP: The ADP process involves pretreatment of ash (milling and caustic leaching), leaching of pretreated ash with nitric acid, roasting of loaded acid solution containing REE, and water leaching of residual from roasting step, resulting in a REE pregnant solution. 2. Solvent Extraction (SX) Upgrading: The SX involves the extraction of REE from a pregnant REE solution using an organic extractant (note after extraction, the aqueous phase was a residual solution and the organic phase contained REE), and stripping of REE from the organic phase product obtained from the extraction using an acid solution (the stripped solution was the final purified product containing REE, organic traces, and traces of other metals for further separation in the electrowinning process). 3. Rare Earth Salts’ (RES) Electrochemical Separation and Purification Process: The staged electrochemical process was separated REO products from the mixed REE solution. Testing by RES was also included in the investigation of options to minimize the solvent extraction steps. This report covers laboratory testing, production of a high purity coal-based REO, process design of the overall REE recovery and purification process, technoeconomic assessment (TEA), and a commercialization plan discussing the overall REE recovery and purification process.

01 COAL, LIGNITE, AND PEAT↗

Development of a Cost-Effective Extraction Process for the Recovery of Heavy and Critical Rare Earth Elements from the Clays and Shales Associated with Coal

The primary objective of the project was to investigate and develop a novel process technology that can extract and concentrate rare earth elements (REE) from coal refuse material, namely shales and clays, to a concentration of greater than or equal to 2% by weight. The extraction and recovery technologies developed in this project leverage the low-cost ion-exchange leaching techniques that are currently applied for commercial heavy rare earth production in South China. In addition to the ion-exchange extraction technology, the project also investigated a novel method of solution concentration and recovery based on ion and/or precipitate flotation.

01 COAL, LIGNITE, AND PEAT↗

High Performance Computing to Enable Next-Generation Low-Temperature Waste Heat Recovery

US manufacturing industry fails to recover an estimated 900 trillion BTUs of low-temperature waste heat from its processes each year. A grand research challenge has been to develop waste heat recovery technology that can be applied to industrial manufacturing processes and vehicle operations. The Oak Ridge National Laboratory (ORNL)/Eaton research team performed computational research and development to design an innovative direct-contact heat exchanger (DCHE) technology to deliver low-cost, compact, longer-lifetime, high-efficiency waste heat recovery that is optimized for a low-temperature organic Rankine cycle. ORNL resources and expertise in high performance computing (HPC) and multiphase flows were utilized to realize this goal while advancing the fundamental understanding of two-phase, two-immiscible-fluid turbulent flow heat transfer for heat exchangers. In the first stage of the project, a computational fluid dynamics (CFD) model of a DCHE was developed. Verification and limited validation of the numerical solution were performed using experimental data from published literature. To support efforts in verification and validation, two-dimensional CFD models were also developed with the objective of investigating different boundary conditions to reach converged, steady-state solutions.Based on benchmarking efforts, a baseline industry-grade design of a DCHE was developed, which consists of two horizontal pipes of different cross-sectional areas – joined by a converging-diverging nozzle in the middle and relies on a three-phase system with co-current flows for operation. Evaporation of the cold liquid (n-pentane or methanol) by the hot liquid water occurs in the first pipe. The first pipe contains two inlets for liquid water and liquid pentane (or liquid methanol). The second pipe with the larger cross-sectional area serves as a gravity-driven phase-separator. It contains two outlets that are staggered to avoid entrainment of the liquid water phase by the gas phase. This baseline design resulted from several trial-and-error evaluations using two-dimensional CFD models. Confirmatory three-dimensional CFD models were also run for different mass flow rates and inlet temperatures (inlet water temperature ranging from 50°C to 90°C), and efficiency plots were produced to fully characterize the proposed industrial-grade design of the DCHE.

97 MATHEMATICS AND COMPUTING↗

Structure and Voltage Recovery Driven by Defects Elimination in Li-Rich Layered Oxide Cathode Materials

Lithium-ion batteries (LIBs) are ubiquitous in a wide range of technologies, including cell phones, electric vehicles, and energy grid, and are indispensable in the transition toward sustainable energy technology. The battery performance is inherently connected to the capability of lithium ions to reversibly intercalate with the electrodes. The capacity of classical layered transition metal (TM) oxides, the primary commercial cathode materials, is limited to cationic redox activity. Anionic redox has thus emerged as a new paradigm for designing novel cathodes for next generation LIBs. It is recently confirmed oxygen redox in lithium-rich layered oxides (LRLO) with composition xLi 2 MnO 3 ∙(1-x)LiTMO 2 , which enables this group of materials exhibit reversible capacities exceeding 280 mAh g -1 . Unfortunately, this material undergoes voltage fading and instability that is rooted in irreversible structural transformation in terms of defects formation including lithium and oxygen vacancies, lithium tetrahedron, TM migration, edge dislocations, stacking fault, and local strain. Modification methods including morphology control, composition gradient, surface treatment, foreign elements doping, etc., have been proposed in the literatures to mitigate the defects formation and maintain the structure reversibility. Despite their improvement, the intrinsic voltage fading is still inevitable and remains a challenge that will require considerable effort to overcome. In this work, we demonstrate a path to recover the layer structure and working voltage through high-temperature annealing. The treatment at high temperature recovers the local Li-excess environments around oxygen, oxygen stacking sequence, and eliminates microstrain associated with different defects. As a result, the voltage profile once more shows plateau region during charge and the average discharge voltage is restored of the cycled cathode after heat treatment. Both theoretical calculations and experimental characterizations illustrate the mechanisms underlying the heating induced recovery. The structure metastability and defects removal are decisive in structure and voltage recovery of LRLO cathode material.

Zhang, Minghao↗

Thermocatalytic Heat Pipes for Geothermal Resource Recovery

Heat pipes are an important technology that allow orders of magnitude faster heat transfer than simple conduction. However, operating principles in heat pipes place fundamental bounds on their performance (critical heat flux and efficiency). Conventional heat pipe functionality is inherently tied to vaporization and condensation of the working fluid charged in the heat pipe. These fluids each have different operating temperature ranges based on the capillary, entrainment, sonic, and boiling limits of the heat pipe design. These limits, typically the capillary limit, dictate the maximum heat flux a heat pipe can carry, and most importantly for geothermal systems, the distance over which the pipes can operate (100 to 200 m maximum under optimum conditions). A thermocatalytic heat pipe breaks the inherent limitations of phase change thermo- and hydrodynamics and can transform heat pipe technology as a potentially more efficient means of extracting heat from a geothermal resource. The thermocatalytic heat pipe uses a working fluid to transport both sensible and chemical heat. An endothermic chemical reaction at depth removes heat from the reservoir and produces reactive intermediates, which are transported to the surface and used to run a reverse exothermic reaction that releases heat for use in power generation or other useful purposes. This technology offers two distinct advantages over conventional geothermal heat recovery technologies: (1) lower heat loss to the rock outside of the geothermal reservoir, and (2) higher heat transfer rates to the well field within the geothermal reservoir. Both advantages offer opportunity to reduce risks and lower costs of geothermal energy recovery. In this report, we discuss an initial effort to assess the efficacy and limitations of this technology for extracting heat from both porous/permeable and nominally impermeable geothermal reservoirs. Numerical simulation capabilities of the STOMP-GT code were enhanced to enable simulations of thermochemical heat pipes traversing geothermal reservoirs. An array of potential thermochemical reaction systems was evaluated and screened. Of these, an ethanol dehydration reaction was most promising in the vapor-liquid reaction set. A solid-phase dehydration reaction (CuSO4·5H2O) showed the highest reaction enthalpy per unit volume but would require development of a nonaqueous carrier fluid to implement it in a heat pipe. Subsurface reservoir simulations predicted long-term performance of the heat pipes for each geothermal reservoir type. The performance of U-shaped wells and coaxial wells was evaluated for a suite of reactions for both hydrothermal and hot dry rock reservoirs and was compared with a baseline case of simply pumping water through the wells. The heat pipe technology was additionally evaluated for an enhanced geothermal system (EGS) with an injection borehole, production borehole, and intervening hydraulically conductive fracture. All reservoir types showed significant improvement in heat recovered over a 20-year operating period ranging from a 1.8X increase for the hot dry rock case to more than 2.5X more energy recovered for the EGS case.

15 GEOTHERMAL ENERGY↗