Conceptual Thermal-Design Options for Pressure-Tube SCWRs With Thermochemical Co-Generation of Hydrogen

Mokry, Sarah; Naidin, M.; Baig, Farina; Gospodinov, Yevgeniy; Zirn, U.; Bakan, Kurtulus; Pioro, Igor; Naterer, G.F.

doi:10.1115/icone16-48313

Cited by 5 publications

(3 citation statements)

References 2 publications

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“…This experimental dataset was obtained within conditions similar to those for proposed SCWR concepts [13]. The dataset was obtained in SCW flowing upward in a 4-m-long vertical bare tube.…”

Section: Scw Heat Transfer Correlationsmentioning

confidence: 99%

Thermalhydraulic analysis and heat transfer correlation for an intermediate heat exchanger linking a SuperCritical Water-cooled Reactor and a Copper-Chlorine cycle for hydrogen co-generation

Mokry

Lukomski

Pioro

et al. 2012

International Journal of Hydrogen Energy

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“…This experimental dataset was obtained within conditions similar to those for proposed SCWR concepts [13]. The dataset was obtained in SCW flowing upward in a 4-m-long vertical bare tube.…”

Section: Scw Heat Transfer Correlationsmentioning

confidence: 99%

Thermalhydraulic analysis and heat transfer correlation for an intermediate heat exchanger linking a SuperCritical Water-cooled Reactor and a Copper-Chlorine cycle for hydrogen co-generation

Mokry

Lukomski

Pioro

et al. 2012

International Journal of Hydrogen Energy

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“…Various recent advances related to the Cu-Cl thermochemical cycle have been reported, in such areas as subprocess analyses [45,46], reactor scale-up [47], energy and exergy analyses of process steps [48][49][50][51] and exergoeconomic analyses [52]. Also, design options for pressure tube SCWRs with thermochemical hydrogen production have recently been examined [53]. The next section aims to simulate the processes within the copper-chlorine thermochemical cycle, and thereby to improve understanding of the cycle so as to allow it to be scaled to a larger size and to be further improved.…”

Section: Copper-chlorine Thermochemical Cyclementioning

confidence: 99%

Nuclear-based hydrogen production with a thermochemical copper-chlorine cycle and supercritical water reactor: equipment scale-up and process simulation

Rosen

Naterer

Chukwu

et al. 2010

Int. J. Energy Res.

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SUMMARY Issues related to equipment scale‐up and process simulation are described for a thermochemical cycle driven by nuclear heat from Canada's proposed Generation IV reactor (Super‐Critical Water‐Cooled Reactor; SCWR), which is a CANDU derivative using supercritical water cooling. The copper–chlorine (Cu‐Cl) cycle has been identified by Atomic Energy of Canada Limited as the most promising cycle for thermochemical hydrogen production with SCWR. Water is decomposed into hydrogen and oxygen through intermediate Cu‐Cl compounds. This article outlines the challenges and design issues of hydrogen production with a Cu‐Cl cycle coupled to Canada's nuclear reactors. The processes are simulated using the Aspen Plus process simulation code, allowing the cycle efficiency and possible efficiency improvements to be examined. The results are useful to assist the development of a lab‐scale cycle demonstration, which is currently being undertaken at the University of Ontario Institute of Technology in collaboration with numerous partners. Copyright © 2010 John Wiley & Sons, Ltd.

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“…Kirillov and his co-workers and adding smaller datasets by other researchers:1. Pioro-Mokry correlation (bulk-fluid-temperature approach)[51,52]:…”

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confidence: 99%

Supercritical-Fluids Thermophysical Properties and Heat Transfer in Power-Engineering Applications

Pioro¹

2020

Advanced Supercritical Fluids Technologies

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Researches on specifics of thermophysical properties and heat transfer at supercritical pressures (SCPs) started as early as the 1930s with the study on free-convection heat transfer to fluids at a near-critical point. In the 1950s, the concept of using SC "steam" to increase thermal efficiency of coal-fired thermal power plants became an attractive option. Germany, USA, the former USSR, and some other countries extensively studied heat transfer to SC fluids (SCFs) during the 1950s till the 1980s. This research was primarily focused on bare circular tubes cooled with SC water (SCW). However, some studies were performed with modeling fluids such as SC carbon dioxide and refrigerants instead of SCW. Currently, the use of SC "steam" in coal-fired thermal power plants is the largest industrial application of fluids at SCPs. Near the end of the 1950s and at the beginning of the 1960s, several studies were conducted to investigate a possibility of using SCW as a coolant in nuclear reactors with the objective to increase thermal efficiency of nuclear power plants (NPPs) equipped with water-cooled reactors. However, these research activities were abandoned for some time and regained momentum in the 1990s. In support of the development of SCW-cooled nuclearpower reactor (SCWR) concepts, first experiments have been started in annular and various bundle flow geometries. At the same time, more numerical and CFD studies have been performed in support of our limited knowledge on specifics of heat transfer at SCPs in various flow geometries. As the first step in this process, heat transfer to SCW in vertical bare tubes can be investigated as a conservative approach (in general, heat transfer in fuel bundles will be enhanced with various types of appendages, that is, grids, end plates, spacers, bearing pads, fins, ribs, etc.). New experiments in the 1990-2000s were triggered by several reasons: (1) thermophysical properties of SCW and other SCFs have been updated from the 1950s-1970s, for example, a peak in thermal conductivity in the critical/ pseudocritical points was "officially" introduced in 1990s; (2) experimental techniques have been improved; (3) in SCWRs, various bundle flow geometries will be used instead of bare-tube geometry; (4) in SC "steam" generators of thermal power plants, larger diameter tubes/pipes (20-40 mm) are used, however in SCWRs hydraulic-equivalent diameters of proposed bundles will be within 5-12 mm; (5) with Research and Development (R&D) of next-generation or Generation-IV nuclear-power-reactor concepts, new areas of application for SCFs have appearedfor example, SCP helium was proposed to be used as a reactor coolant, SCP Brayton 1 and Rankine cycles with SC carbon dioxide as a working fluid are being developed, etc. A comparison of thermophysical properties of SCFs with those of subcriticalpressure fluids showed that SCFs as single-phase fluids have unique properties, which are close to "liquid-like" behavior below critical or pseudocritical points and are quite similar to the behavior of "gas-li...

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Conceptual Thermal-Design Options for Pressure-Tube SCWRs With Thermochemical Co-Generation of Hydrogen

Cited by 5 publications

References 2 publications

Thermalhydraulic analysis and heat transfer correlation for an intermediate heat exchanger linking a SuperCritical Water-cooled Reactor and a Copper-Chlorine cycle for hydrogen co-generation

Thermalhydraulic analysis and heat transfer correlation for an intermediate heat exchanger linking a SuperCritical Water-cooled Reactor and a Copper-Chlorine cycle for hydrogen co-generation

Nuclear-based hydrogen production with a thermochemical copper-chlorine cycle and supercritical water reactor: equipment scale-up and process simulation

Supercritical-Fluids Thermophysical Properties and Heat Transfer in Power-Engineering Applications

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