Engineering Papers⌕ Search

SEARCH · Engineering Papers

Results for “Tanks”

Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.

At least 1,099 records · Page 61

Estimating the Rate of Solids Accumulation in Double Shell Tanks - 17093

This project describes a method of estimating the rate of solids accumulation in Low Activity Waste Pretreatment System (LAWPS) Double Shell Tanks (DSTs) from solids entrainment and precipitation in order to identify and recommend appropriate control measures to protect LAWPS feed schedules. By comparing various volume fraction solids in transfer volumes with the available tank storage needed to maintain LAWPS feed schedules the number of possible transfers before solids removal is necessary can be determined. A family of curves spanning the range of values of volume fraction solids most frequently observed in grab samples was charted to show the transfer batch number at which point accumulated solids inhibit sufficient storage for waste feed schedules and thereby warrant solids removal. Results of this study indicate that in order to preclude solids removal activities during the LAWPS waste transfers, volume fraction settled solids levels in LAWPS transfers are required to stay below 0.0133 and 0.0183 for Feed Staging Tank 1 and 2, respectively. Results of this study show that the rate of solids accumulation will exceed the requirement, and therefore solids removal capability for LAWPS DSTs upgrades is required. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Advances in the glass formulations for the Hanford Tank Waste Treatment and Immobilization Plant - 15053

The Department of Energy-Office of River Protection (DOE-ORP) is constructing the Hanford Tank Waste Treatment and Immobilization Plant (WTP) to treat radioactive waste currently stored in underground tanks at the Hanford site in Washington. The WTP that is being designed and constructed by a team led by Bechtel National, Inc. (BNI) will separate the tank waste into High Level Waste (HLW) and Low Activity Waste (LAW) fractions with the majority of the mass (∼90%) directed to LAW and most of the activity (>95%) directed to HLW. The pretreatment process, envisioned in the baseline, involves the dissolution of aluminum-bearing solids so as to allow the aluminum salts to be processed through the cesium ion exchange and report to the LAW Facility. There is an oxidative leaching process to affect a similar outcome for chromium-bearing wastes. Both of these unit operations were advanced to accommodate shortcomings in glass formulation for HLW inventories. A by-product of this are a series of technical challenges placed upon materials selected for the processing vessels. The advances in glass formulation play a role in revisiting the flow sheet for the WTP and hence, the unit operations that were being imposed by minimal waste loading requirements set forth in the contract for the design and construction of the plant. Another significant consideration to the most recent revision of the glass models are the impacts on resolution of technical questions associated with current efforts for design completion. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Decommissioning sodium dump tanks - 15547

The Nuclear Decommissioning Authority (NDA) is a non-departmental public body of the UK Government responsible for managing the effective and efficient clean-up of the UK's nuclear legacy. DSRL (Dounreay Site Restoration Limited, a wholly-owned subsidiary of the Cavendish Dounreay Partnership Ltd, a consortium of Cavendish Nuclear, CH2M HILL and URS) is the site licence company operating under contract to the NDA and funded by the NDA for the clean-up and demolition of the Dounreay Site, Britain's former centre of fast reactor research and development, near Thurso, Scotland, including decommissioning the Dounreay Prototype Fast Reactor (PFR). The plutonium metal fuel PFR was the second and last fast reactor to be built in the UK, with construction commencing in 1968. The reactor closed in 1994 and was de-fuelled, but the reactive sodium remaining in the cooling system required decommissioning, and approximately 12 tonnes of low level waste (LLW) sodium remained in the un-heated dump tanks. This paper highlights the approach used for decommissioning the dump tanks and their contents. The sodium was removed as a solid at ambient temperature, packaged, and staged for destruction at a later date. The tanks and pipework were then cleaned, size reduced and packaged for disposal as LLW. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Determination of Erosion/Corrosion Rates in Hanford Tank Farms Radioactive Waste Transfer System Pipelines - 16395

The twenty-eight double-shell underground radioactive waste storage tanks at the U.S. Department of Energy's Hanford Site near Richland, WA are interconnected by the Waste Transfer System network of buried steel encased pipelines and pipe jumpers in below-grade pits. The pipeline material is stainless steel or carbon steel in 51 mm to 152 mm (2 in. to 6 in.) sizes. The pipelines carry slurries ranging up to 20 volume percent solids and supernatants with less than one volume percent solids at velocities necessary to prevent settling. The pipelines, installed between 1976 and 2011, were originally intended to last until the 2028 completion of the double-shell tank storage mission. The mission has been subsequently extended. In 2010 the Tank Operating Contractor began a systematic evaluation of the Waste Transfer System pipeline conditions applying guidelines from API 579-1/ASME FFS-1 (2007), Fitness-For- Service. Between 2010 and 2014 Fitness-for-Service examinations of the Waste Transfer System pipeline materials, sizes, and components were completed. In parallel, waste throughput histories were prepared allowing side-by-side pipeline wall thinning rate comparisons between carbon and stainless steel, slurries and supernatants and throughput volumes. The work showed that for transfer volumes up to 6.1 E+05 m{sup 3} (161 million gallons), the highest throughput of any pipeline segment examined, there has been no detectable wall thinning in either stainless or carbon steel pipeline material regardless of waste fluid characteristics or throughput. The paper describes the field and laboratory evaluation methods used for the Fitness-for-Service examinations, the results of the examinations, and the data reduction methodologies used to support Hanford Waste Transfer System pipeline wall thinning conclusions. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Robotic Tank Refurbishment System (TRS) for U.S. Naval Vessels - 18395

A remotely-operated Tank Refurbishment System (TRS) has been developed to reduce the personnel hazards associated with manual refurbishment of U.S. Naval vessel tanks. This system is capable of using a variety of tools to complete the necessary refurbishment tasks within the tanks. In 2017, the design for this system was completed, and preliminary testing was successfully completed. (authors)

42 ENGINEERING↗

Repurposing Hanford Waste Tank AP-106 for Interim Storage of Treated Low-Activity Waste - 20044

Hanford Double-Shell Tank AP-106 is being repurposed to serve as the lag storage tank holding feed for the Direct Feed Low-Activity Waste (DFLAW) process at the Waste Treatment and Immobilization Plant (WTP). The repurposing process is the sequence of tank additions and transfers that will remove the Cs 137 inventory from AP-106. The repurposing process steps are designed to remove Cs-137 more effectively and efficiently as compared to regular supernatant transfers. The process steps are estimated to take 2-months to complete. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Application of On-Line Monitoring and Real-Time Characterization of Low Level Waste Samples from Hanford Tanks - 20380

Waste and treatment stream characterization is an essential part of safe, efficient, and cost-effective processing of Hanford materials. The demand for materials characterization, including chemical, radionuclide, and physical attributes during waste management, transfer, and staging operations in the Hanford tank farms, is expected to significantly increase as the U.S. Department of Energy Office of River Protection (ORP) progresses toward Hanford waste treatment and immobilization. The application of on-line monitoring can greatly improve operation time frames and reduce costs by providing real-time data and supporting the reduction of necessary grab sample collection. Recently, our team applied Raman online monitoring and chemometric modeling to the supernate of Hanford tank 241-AP-105, and demonstrated the quantitative measurement of nine analytes within this waste. Application of this method has been expanded to additional Hanford tank wastes, AW-102 and AP-107. The performance of the process monitoring instruments and the accuracy of the chemometric models will be assessed. On-line monitoring results will be compared to anion results determined from the current standard, ion-chromatographic and inductively coupled plasma mass spectrometry methods. Comparisons of both determined values and uncertainties of results will be presented. Results will be shared with personnel working on flowsheet interfaces for the Direct-Feed Low Activity Waste mission at Hanford. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Progress towards the POCO of UK Highly Active Storage Tanks - 20112

In the UK Highly Active (HA) waste is stored in stainless steel Highly Active Storage Tanks (HASTs) prior to encapsulation in glass in one of three operating vitrification plants. Significant progress has been made towards the reduction in the volume of HA Liquor (HAL) stored in these HASTs and several tanks currently operate at heel levels. In recent years a strategy has been developed towards the Post Operational Clean Out (POCO) of the tanks and significant progress has been made in confirming this strategy since it was last presented at WMS [1]. For a variety of reasons changes to associated operational assumptions have also been made. This paper will highlight recent progress and changes associated with the strategy, including a description of some of the challenges that have been overcome and associated technical work undertaken. It will also detail current plans to POCO the HASTs, as quickly as possible, while minimising the risk and continuing to support other ongoing reprocessing and clean-up programmes as part of the overall UK clean-up mission. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Determining Drying Conditions to Mitigate Hanford Double Shell Storage Tank Underside Corrosion — Phase 1

The Hanford Site in Washington State has legacy radiological waste that is being retrieved from single shell tanks (SSTs) and transferred to newer, double shell tanks (DSTs) for eventual closure of the SSTs. The waste is maintained in the DSTs until eventual immobilization can be performed at the Waste Treatment and Immobilization Plant (WTP), currently under construction. Until full immobilization is complete, extended service of the DSTs must be ensured by mitigating corrosion of the steel tank walls and buried steel pipelines. A Pit Air Supply System has been developed to mitigate corrosion of the leak detection pits connected to the concrete foundations of the DSTs. The objectives for the present study are: (i) to corrode steel specimens in an electrolytic simulant to form artificial pits with specific pit depths, and (ii) to determine the temperature and humidity levels that will mitigate further pit growth. Experimental work and results will be presented to evaluate conditions associated with the PASS system and predict corrosion rates when the PASS is operating.

Atmospheric Corrosion↗

Hanford Tank Waste Technology Development Integration and Innovation Synergy

The Chief Technology Office (CTO) within Hanford Tank Waste Operations & Closure (H2C) identifies technology development needs and develops solutions for tank waste treatment. One key element of the technology development (TD) program is the annual Technology Development Integrated Coordination (TDIC) meeting series. The main goal of these meetings is to inform the National Laboratories and other entities of the needs identified by the end users of the technology. In turn, the meetings provide an opportunity for National Laboratories and others to provide insight into potential solutions. This dynamic facilitates dialogues that frequently identify not only new, innovative approaches, but also enhancements to ongoing technology development projects.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Online, real-time analysis of highly complex processing streams: Quantification of analytes in Hanford tank sample

Processing of hazardous materials is a crucial example of where on-line monitoring can significantly reduce operation risk, cost, and time. This is particularly true in the case of the Hanford site, where nuclear materials from the cold war era are being processed for environmental cleanup efforts. In exceedingly complex streams such as those at Hanford, on-line and real-time monitoring can be a challenge due to complexity of signals. Further obstacles are imposed by the caustic nature of processing streams as well as the radiation damage inflicted on instruments and probes. On-line monitoring based on Raman spectroscopy enables the detection of many Hanford tank species of interest, and was demonstrated here on nine chemical species that comprise the majority of tank waste by volume, including Al(OH)4-, C2O42-, CO32-, CrO42-, NO32-, NO3-, OH-, PO43-, SO42-. Real-time analysis of Raman signal allows for immediate quantification of target analytes and was successfully accomplished through the use of chemometric models. Furthermore, irradiation tests reveal Raman monitoring systems can effectively continue to operate even after receiving 1·107 Rad of gamma dose. The on-line, real-time monitoring system developed here was successfully used to simultaneously quantify nine target analytes in a real samples collected from Hanford tank AP-105.

Lines, Amanda M.↗

Design of a reconfigurable liquid hydrogen fuel tank for use in the Genii unmanned aerial vehicle

Long endurance flight, on the order of days, is a leading flight performance characteristic for Unmanned Aerial Vehicles (UAVs). Liquid hydrogen (LH2) is well suited to providing multi-day flight times with a specific energy 2.8 times that of conventional kerosene based fuels. However, no such system of LH2 storage, delivery, and use is currently available for commercial UAVs. In this paper, we develop a light weight LH2 dewar for integration and testing in the proton exchange membrane (PEM) fuel cell powered, student designed and constructed, Genii UAV. The fuel tank design is general for scaling to suit various UAV platforms. A cylindrical vacuum-jacketed design with removable end caps was chosen to incorporate various fuel level gauging, pressurizing, and slosh mitigation systems. Heat and mechanical loadings were modeled to compare with experimental results. Mass performance of the fuel tank is characterized by the fraction of liquid hydrogen to full tank mass, and the insulation performance was characterized by effective thermal conductivity and boil-off rate.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Integrated heat exchanger design for a cryogenic storage tank

Field demonstrations of liquid hydrogen technology will be undertaken for the proliferation of advanced methods and applications in the use of cryofuels. Advancements in the use of cryofuels for transportation on Earth, from Earth, or in space are envisioned for automobiles, aircraft, rockets, and spacecraft. These advancements rely on practical ways of storage, transfer, and handling of liquid hydrogen. Focusing on storage, an integrated heat exchanger system has been designed for incorporation with an existing storage tank and a reverse Brayton cycle helium refrigerator of capacity 850 watts at 20 K. The storage tank is a 125,000-liter capacity horizontal cylindrical tank, with vacuum jacket and multilayer insulation, and a small 0.6-meter diameter manway opening. Addressed are the specific design challenges associated with the small opening, complete modularity, pressure systems re-certification for lower temperature and pressure service associated with hydrogen densification, and a large 8:1 length-to-diameter ratio for distribution of the cryogenic refrigeration. The approach, problem solving, and system design and analysis for integrated heat exchanger are detailed and discussed. Implications for future space launch facilities are also identified. The objective of the field demonstration will be to test various zero-loss and densified cryofuel handling concepts for future transportation applications.

42 ENGINEERING↗

Modeling and Simulating Diffused Aeration for Hydrogen Removal from Expansion Tanks of Parabolic Trough Solar Thermal Power Plants

High-temperature decomposition of organic heat transfer fluids (HTFs) can cause hydrogen build-up in the receiver annulus of parabolic trough power plants. This build-up increases the receiver thermal losses and results in a decline in power output. Prior work has shown that removal of hydrogen from the expansion tank can be an effective mitigation strategy. This paper presents a modeling methodology and simulation results for passive and diffused aeration removal of hydrogen from the expansion tank. Focus is on estimating the mass transfer of hydrogen from the HTF into the headspace gas across the surface and bubble liquid/gas interfaces. Simulations for the operation conditions and expansion tank geometry of the Nevada Solar One power plant (located near Las Vegas, Nevada, USA) show that passive removal (surface mass transfer only) may be sufficient to obtain hydrogen removal rates of 1.7 x 10-4 mol/s (minimal removal rate necessary). A diffused aeration system (surface plus bubble mass transfer) with gas injection volume rates up to 100 L/s may be necessary to obtain a hydrogen removal rate of 2.0 x 10-4 mol/s (optimal removal rate).

14 SOLAR ENERGY↗

Hanford Tank Waste Matrix Impact on Ion Exchange Performance Using Crystalline Silicotitanate

The removal of radiocesium from Hanford tank waste supernate is a critical step in preparing feed for low-activity waste immobilization. This study evaluated cesium ion exchange performance using crystalline silicotitanate (CST) media in a series of tests designed to evaluate the influence of waste matrix variability on capacity and kinetics. Tank waste supernate subsampled from five Hanford double-shell tanks encompassed a range of sodium, hydroxide, nitrate, and nitrite concentrations in order to assess the impact of feed variability on the performance of the ion exchange system. Both equilibrium and dynamic ion exchange tests were conducted to quantify cesium distribution coefficients and breakthrough behavior under prototypic operating conditions. Results indicated that effective cesium capacity varied by up to a factor of five across the matrices tested, with higher sodium concentrations significantly reducing uptake. Kinetic behavior was similarly matrix-dependent, with solution viscosity contributing to a twofold variation in mass-transfer rates. These results demonstrate the strong dependence of CST ion exchange performance on waste composition and must be incorporated into predictive models for future treatment system design and optimization.

Westesen, Amy M.↗

Is Radioactive Tank Waste a Bingham Fluid?

Slurries and sludges across the United States Department of Energy (DOE) complex rank among the most rheologically interesting. Their composition is heterogeneous, spanning a very broad range of particle sizes, densities, and interparticle forces. All exhibit shear thinning, some have yield stresses, and many are thixotropic. Despite the variety, these complex fluids are often represented using the historic Bingham fluid model, which fits higher shear rate data to a simple straight line. The intercept provides a yield stress, which has been a key design parameter in construction of large-scale waste processing facilities. However, many radioactive wastes are simply not Bingham fluids, which extrapolate but poorly across low to intermediate shear rates that are characteristic of typical processing conditions. Indeed, processing shear rates as high as 200 1/s, which has been a typical minimum shear rate used in fitting, are seldom encountered in nuclear waste processing. Therefore, more realistic rheological models are necessary to accurately predict waste processing performance. PNNL recently re-evaluated the rheology of reconstituted Hanford REDOX sludge waste against a wide variety of rheological models including the Bingham, Cross, Cross with yield stress, Carreau, biviscous, Herschel-Bulkley (which includes a power law dependence), Casson, and Gay models. They found that all of the models provided a closer fit than the Bingham model and that the biviscous model and Cross with yield stress model were convincing. However, reconstituted Hanford REDOX sludge waste is but one type of DOE waste and a direct contrast and comparison of these three models against undiluted, unmixed tank waste (actual not simulant) has not been performed previously. Therefore, the purpose of this paper is to evaluate the rheology of actual tank waste with these more accurate rheological models. In this paper, we evaluate select rheological data for slurry samples from Hanford’s AZ-101, AZ-102, and SY-101 waste tanks. In each of these cases, we find that Cross’ model with yield stress and the biviscous model significantly outperform the Bingham fluid model. Furthermore, the AZ-101 data also shows that the shear stress peak that startup significantly exceeds the Bingham yield stress, which is commonly observed in the incipient moments of rheological measurements on simulants. In contrast, Cross’ model may empirically accommodate an initial spike in shear stress at modest shear rates. These are important observations because computational and analytical fluid dynamics simulations rely on rheological constitutive models for accurately and conservatively predict waste processing performance. These findings suggest the need for better rheological modeling of and validation against radioactive waste.

Rheology, Radioactive Waste↗

MO-FG-202-03: Efficient Data Collection of Continuous 2D and Discrete Relative Dosimetric Data for Annual LINAC QA Using TrueBeam Developer Mode and a 1D Scanning Tank

Purpose: To develop a method to exploit real-time dynamic machine and couch parameter control during linear accelerator (LINAC) beam delivery to facilitate efficient performance of TG-142 suggested, Annual LINAC QA tests. Methods: Varian’s TrueBeam Developer Mode (Varian Medical Systems, Palo Alto, CA) facilitates control of Varian’s TrueBeam LINAC via instructions provided in Extensible Markup Language (XML) files. This allows machine and couch parameters to be varied dynamically, in real-time, during beam delivery. Custom XML files were created to allow for the collection of (1) continuous Tissue Maximum Ratios (TMRs), (2) beam profiles, and (3) continuous output factors using a 1D-scanning tank. TMRs were acquired by orienting an ionization chamber (IC) at isocenter (depth=25cm) and synchronizing a depth scan towards the water surface while lowering the couch at 1mm/s. For beam profiles, the couch was driven laterally and longitudinally while logging IC electrometer readings. Output factors (OFs) where collected by continually varying field sizes (4×4 to 30×30-cm{sup 2}) at a constant speed of 6.66 mm/s. To validate measurements, comparisons were made to data collected using traditional methods (e.g. 1D or 3D tank). Results: All data collecting using the proposed methods agreed with traditionally collected data (TMRs within 1%, OFs within 0.5% and beam profile agreement within 1% / 1mm) while taking less time to collect (factor of approximately 1/10) and with a finer sample resolution. Conclusion: TrueBeam developer mode facilitates collection of continuous data with the same accuracy as traditionally collected data with a finer resolution in less time. Results demonstrate an order of magnitude increase in sampled resolution and an order of magnitude reduction in collection time compared to traditional acquisition methods (e.g. 3D scanning tank). We are currently extending this approach to perform other TG-142 tasks.

61 RADIATION PROTECTION AND DOSIMETRY↗