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Mark H. Anderson
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Journal Articles
Article Type: Research Papers
J. Thermal Sci. Eng. Appl. June 2021, 13(3): 031017.
Paper No: TSEA-20-1006
Published Online: November 4, 2020
Abstract
The Homogenized Heat Exchanger Thermohydraulic (HHXT) modeling environment has been developed to provide thermodynamic modeling of printed circuit heat exchangers (PCHEs). This finite element approach solves solid conduction and fluid thermohydraulics simultaneously, without the need to mesh the minuscule micro-channels of a PCHE. The model handles PCHE features such as headers, solid side walls, and channel inlet and outlet regions, in addition to the micro-channel core. The HHXT model resolves PCHE thermohydraulics using simple model definitions and minimum computational overhead, making it an ideal design tool. This work introduces the thermohydraulic model at the core of HHXT. The homogenization approach used in the model occupies a medium between simplified linear analyses of heat transfer within a PCHE and the brute force of a fully resolved finite element, or computational fluid dynamics, model. An example problem modeling an experimental PCHE is presented. The ability of the HHXT model to simulate fluid flow through a directional varying micro-channel core of two heat-exchanging streams is demonstrated. The HHXT model is being distributed for free within the research community.
Proceedings Papers
Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A092, July 14–19, 2019
Paper No: PVP2019-93773
Abstract
Compact and thermally efficient, Printed Circuit Heat Exchangers (PCHEs) are favored for use in next generation nuclear power plants. Containing thousands of small working fluid channels distributed in a solid 316H or 800H block, PCHEs can handle high pressures and operating temperatures required by generation IV nuclear plants. Advanced nuclear reactors will require the certification of a nuclear service PCHE design by construction codes, such as BPVC Sec-3. Compliance with this standard requires Creep fatigue and ratcheting analyses be performed for expected loading service transients. Realizing this analysis in PCHEs requires a simplified and flexible modeling approach that can be run over dozens of transients for multiple heat exchanger geometries. The Rich Environment Heatex-changer Transient (REHT) model is being developed to provide a full PCHE model needed to properly resolve Sec-3 loading conditions without the complexity inherent in resolving all facets of the PCHE geometry. This work introduces the thermohydraulic model that is the core of the REHT model. An example problem modeling an experimental scaled PCHE is presented. The ability of the REHT model to simulate fluid flow through a directional varying microchannel core of two heat exchanging streams is demonstrated. The REHT model resolves PCHE thermohydraulics using simple model definitions and minimum computational overhead, making it an ideal design tool.
Proceedings Papers
Proc. ASME. ES2016, Volume 1: Biofuels, Hydrogen, Syngas, and Alternate Fuels; CHP and Hybrid Power and Energy Systems; Concentrating Solar Power; Energy Storage; Environmental, Economic, and Policy Considerations of Advanced Energy Systems; Geothermal, Ocean, and Emerging Energy Technologies; Photovoltaics; Posters; Solar Chemistry; Sustainable Building Energy Systems; Sustainable Infrastructure and Transportation; Thermodynamic Analysis of Energy Systems; Wind Energy Systems and Technologies, V001T04A018, June 26–30, 2016
Paper No: ES2016-59615
Abstract
Supercritical Carbon Dioxide (sCO2) power cycles have the potential to deliver high efficiency at low cost. However, in order for s-CO2 cycle to reach high efficiency, highly effective recuperators are needed. These recuperative heat exchangers must transfer heat at a rate that is substantially larger than the heat transfer to the cycle itself and can therefore represent up to 24% of the total power block cost in a recompression Brayton cycle [1]. Lower cost regenerators are proposed as a cost saving alternative to high cost printed circuit recuperators. A regenerator is a heat exchanger that alternately has hot and cold fluid passing through it. During the first half of its cycle the hot gas is passed over a storage media bed (stainless steel balls, screens, or similar fill material) where thermal energy is stored. During the next half of the cycle, cold fluid is passed through in the opposite direction, extracting the thermal energy from the bed. By operating a cycle with two (or more) regenerators, where one is always in a hot to cold (HTC) blow and the other in a cold to hot blow (CTH), a quasi-steady state can be achieved in the cycle to allow continuous operation. A model of the regenerator was created and used in place of a recuperator in a model of a 10MW power plant. The thermal effectiveness of the regenerator cycle was slightly lower than the recuperator cycle, however the regenerator cycle had a saving of about 9.3 percent in the Levelized Cost of Energy (LCoE). A scale model of the regenerator is under construction which will verify the performance of the regenerator model.
Journal Articles
Luke C. Olson, Roderick E. Fuentes, Michael J. Martinez-Rodriguez, James W. Ambrosek, Kumar Sridharan, Mark H. Anderson, Brenda L. Garcia-Diaz, Joshua Gray, Todd R. Allen
Journal:
Journal of Solar Energy Engineering
Article Type: Research-Article
J. Sol. Energy Eng. December 2015, 137(6): 061007.
Paper No: SOL-14-1286
Published Online: October 15, 2015
Abstract
The effects of crucible material choice on alloy corrosion rates in immersion tests in molten LiF–NaF–KF (46.5–11.5-42 mol. %) salt held at 850 °C for 500 hrs are described. Four crucible materials were studied. Molten salt exposures of Incoloy-800H in graphite, Ni, Incoloy-800H, and pyrolytic boron nitride (PyBN) crucibles all led to weight-loss in the Incoloy-800H coupons. Alloy weight loss was ∼30 times higher in the graphite and Ni crucibles in comparison to the Incoloy-800H and PyBN crucibles. It is hypothesized galvanic coupling between the alloy coupons and crucible materials contributed to the higher corrosion rates. Alloy salt immersion in graphite and Ni crucibles had similar weight-loss hypothesized to occur due to the rate limiting out diffusion of Cr in the alloys to the surface where it reacts with and dissolves into the molten salt, followed by the reduction of Cr from solution at the molten salt and graphite/Ni interfaces. Both the graphite and the Ni crucibles provided sinks for the Cr, in the formation of a Ni–Cr alloy in the case of the Ni crucible, and Cr carbide in the case of the graphite crucible.
Journal Articles
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041010.
Paper No: NERS-15-1017
Published Online: September 3, 2015
Abstract
Li 2 BeF 4 , or flibe, is the primary candidate coolant for the fluoride-salt-cooled high-temperature nuclear reactor (FHR). Kilogram quantities of pure flibe are required for repeatable corrosion tests of modern reactor materials. This paper details fluoride salt purification by the hydrofluorination–hydrogen process, which was used to regenerate 57.4 kg of flibe originating from the secondary loop of the molten salt reactor experiment (MSRE) at Oak Ridge National Laboratory (ORNL). Additionally, it expounds upon necessary handling precautions required to produce high-quality flibe and includes technological advancements which ease the purification and analysis process. Flibe batches produced at the University of Wisconsin are the largest since the MSRE program, enabling new corrosion, radiation, and thermal hydraulic testing around the United States.
Journal Articles
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031001.
Paper No: NERS-14-1043
Published Online: May 20, 2015
Abstract
Experiments were performed to investigate the effects of buoyancy on heat transfer characteristics of supercritical carbon dioxide in heating mode. Turbulent flows with Reynolds numbers up to 60,000, at operating pressures of 7.5, 8.1, and 10.2 MPa, were tested in a round tube. Local heat transfer coefficients were obtained from measured wall temperatures over a large set of experimental parameters that varied inlet temperature from 20 to 55°C, mass flux from 150 to 350 kg / m 2 s , and a maximum heat flux of 65 kW / m 2 . Horizontal, upward, and downward flows were tested to investigate the unusual heat transfer characteristics due to the effect of buoyancy and flow acceleration caused by large variation in density. In the case of upward flow, severe localized deterioration in heat transfer was observed due to reduction in the turbulent shear stress and is characterized by a sharp increase in wall temperature. In the case of downward flow, turbulent shear stress is enhanced by buoyancy forces, leading to an enhancement in heat transfer. In the case of horizontal flow, flow stratification occurred, leading to a circumferential variation in wall temperature. Thermocouples mounted 180° apart on the tube revealed that the wall temperatures on the top side are significantly higher than the bottom side of the tube. Buoyancy factor calculations for all the test cases indicated that buoyancy effects cannot be ignored even for horizontal flow at Reynolds numbers as high as 20,000. Experimentally determined Nusselt numbers are compared to existing correlations available in the literature. Existing correlations predicted the experimental data within ± 30 % , with maximum deviation around the pseudocritical point.
Proceedings Papers
Stuart R. Slattery, Tamara L. Malaney, Scott J. Weber, Mark H. Anderson, Kumar Sridharan, Todd R. Allen
Proc. ASME. HTR2008, Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2, 691-698, September 28–October 1, 2008
Paper No: HTR2008-58053
Abstract
An experimental system for in situ high temperature measurements of spectral emissivity of VHTR materials has been designed and constructed. The design consists of a cylindrical block of silicon carbide with several machined cavities for placement of test samples, as well as a black body cavity. The block is placed inside a furnace for heating to temperatures up to 1000°C. A shutter system allows for selective exposure of any given test sample for emissivity measurements. An optical periscope guides the thermal radiation from the sample to a Fourier Transform Infra Red (FTIR) spectrometer which is used for real-time measurements of spectral emissivity over a wavelength range of 0.8μm to 10μm. To specifically address the needs of VHTR applications, the system has been designed for studies with VHTR grade helium environments and air transients. Inlet and outlet gas compositions are measured using a gas chromatograph, which in conjunction with ex situ analysis of the samples by electron microscopy and x-ray diffraction will allow for the correlation of surface corrosion of the materials and their spectral emissivities under different operating and accident conditions.
Proceedings Papers
Dae H. Cho, Richard J. Page, Sherif H. Abdulla, Mark H. Anderson, Helge B. Klockow, Michael L. Corradini
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 125-131, April 25–29, 2004
Paper No: ICONE12-49284
Abstract
Experiments on melt quenching by the injection of water from below were conducted. The test section represented one-dimensional flow-channel simulation of the bottom injection of water into a core melt in the reactor cavity. The melt simulant was lead-bismuth alloy. For the experimental conditions employed (i.e., melt depth and water flow rates), it was found that: 1) the volumetric heat removal rate increased with increasing water mass flow rate and 2) the non-condensable gas mixed with the injected water had no impairing effect on the overall heat removal rate. Implications of these findings for ALWR ex-vessel coolability are discussed.