Parametric evaluation of large-scale high-temperature electrolysis hydrogen production using different advanced nuclear reactor heat sources

Harvego, Edwin A.; McKellar, Michael G.; O’Brien, James E.; Herring, J. Stephen

doi:10.1016/j.nucengdes.2009.03.003

Cited by 21 publications

(14 citation statements)

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“…In addition to steam electrolysis, SOECs can be used to electrolyze CO 2 for CO and O 2 production [33][34][35][36][37][38][39]. Co-electrolysis of CO 2 and H 2 O has also been demonstrated to be feasible for simultaneous production of H 2 and CO [33][34][35][36][37][38][39][40][41][42][43][44], which can be subsequently processed for synthetic fuel production.…”

Section: Introductionmentioning

confidence: 99%

“…Co-electrolysis of CO 2 and H 2 O has also been demonstrated to be feasible for simultaneous production of H 2 and CO [33][34][35][36][37][38][39][40][41][42][43][44], which can be subsequently processed for synthetic fuel production. In an SOEC used for H 2 O/CO 2 co-electrolysis, 3 reactions take place simultaneously, namely H 2 O electrolysis, CO 2 electrolysis, and reversible water gas shift reaction (WGSR).…”

Section: Introductionmentioning

confidence: 99%

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An electrochemical model for syngas production by co-electrolysis of H2O and CO2

2012

Journal of Power Sources

163

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Co-electrolysis of CO 2 and H 2 O in a solid oxide electrolyzer cell (SOEC) offers a promising way for syngas production. In this study, an electrochemical model is developed to simulate the performance of an SOEC used for CO 2 /H 2 O co-electrolysis, considering the reversible water gas shift reaction (WGSR) in the cathode. The dusty gas model (DGM) is used to characterize the multi-component mass transport in the electrodes. The modeling results are compared with experimental data from the literature and good agreement is observed. Parametric simulations are performed to analyze the distributions of WGSR and gas composition in the electrode. A new method is proposed to quantify the contribution of WGSR to CO production by comparing the CO fluxes at the cathode-electrolyte interface and at the cathode surface. It is found that the reversible WGSR could contribute to CO production at a low operating potential but consume CO at a high operating potential. In addition, the contribution of WGSR to CO production also depends on the operating temperature and inlet gas composition.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

An electrochemical model for syngas production by co-electrolysis of H2O and CO2

2012

Journal of Power Sources

163

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“…With only a fraction of the total coolant flow rejecting its heat to the precooler at a sink temperature of 36°C, the power cycle heat rejection rate (waste heat) is 305 MW. This compares to a waste heat rejection rate of approximately 358 MW for an equivalent direct helium Brayton power plant cycle powered by a 600 MW t reactor at a reactor outlet temperature of 750°C [11]. The waste heat rejection rate for the supercritical CO 2 recompression Brayton cycle is, therefore, approximately 15% less than that of the equivalent recuperated helium Brayton cycle, contributing to the overall higher thermal efficiency of the supercritical CO 2 recompression Brayton power plant cycle.…”

Section: Direct Supercritical Co 2 Recompression Brayton Power Plant mentioning

confidence: 89%

Optimization and Comparison of Direct and Indirect Supercritical Carbon Dioxide Power Plant Cycles for Nuclear Applications

Harvego

McKellar

2011

Volume 4: Energy Systems Analysis, Thermodynamics and Sustainability; Combustion Science and Engineering; Nanoengineering for E

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Results of analyses performed using the UniSim process analyses software to evaluate the performance of both a direct and indirect supercritical CO 2 Brayton power plant cycle with recompression at different reactor outlet temperatures are presented. The direct supercritical CO 2 power plant cycle transferred heat directly from a 600 MW t reactor to the supercritical CO 2 working fluid supplied to the turbine generator at approximately 20 MPa. The indirect supercritical CO 2 cycle assumed a helium-cooled Very High Temperature Reactor (VHTR), operating at a primary system pressure of approximately 7.0 MPa, delivered heat through an intermediate heat exchanger to the secondary indirect supercritical CO 2 recompression Brayton cycle, again operating at a pressure of about 20 MPa. For both the direct and indirect power plant cycles, sensitivity calculations were performed for reactor outlet temperature between 550°C and 850°C.The UniSim models used realistic component parameters and operating conditions to model the complete reactor and power conversion systems. CO 2 properties were evaluated, and the operating ranges of the cycles were adjusted to take advantage of the rapidly changing properties of CO 2 near the critical point. The results of the analyses showed that, for the direct supercritical CO 2 power plant cycle, thermal efficiencies in the range of approximately 40 to 50% can be achieved over the reactor coolant outlet temperature range of 550°C to 850°C. For the indirect supercritical CO 2 power plant cycle, thermal efficiencies were approximately 11 -13% lower than those obtained for the direct cycle over the same reactor outlet temperature range. NOMENCLATURE INTRODUCTIONThis study provides an evaluation and comparison of the performance of direct and indirect supercritical CO 2 power plant cycles operating in a reactor outlet temperature range between 550°C and 850°C. The power plant cycle selected for this study is referred to as a supercritical CO 2 closed Brayton cycle (also known as the Joule cycle) with recompression.This power plant cycle was originally described by Dostal in his ScD Thesis/Topical Report [1], and subsequently referenced in a variety of other publications [2][3][4][5][6][7][8][9].The Next Generation Nuclear Plant (NGNP) is a proposed full scale facility to be used to demonstrate the commercial potential of a high temperature gas-cooled nuclear reactor for electricity and process heat applications.The current reference design for the NGNP is a helium-cooled Very High Temperature Reactor (VHTR) operating with a 750°C reactor coolant outlet temperature. For NGNP applications, the supercritical CO 2 recompression Brayton cycle would be operated as an indirect power conversion cycle, in which the helium-cooled VHTR, operating at a primary system pressure of approximately 7.0 MPa, delivers heat through an intermediate heat exchanger to the secondary indirect supercritical CO 2 recompression Brayton cycle operating at a pressure of about 20 MPa. However, the direct supercritical

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“…Harvego et al [19] provided a comparison of advanced nuclear reactors capable of operating at reactor outlet temperatures of 600 to 900 °C and found that the hydrogen production efficiencies could range between 25 and 55%. For comparison, the best hydrogen-production efficiencies range from 60 to 80% [20] depending on the system design Figure 4: HYSYS flow sheet model of modified HTSEP that has additional heat recuperation.…”

Section: Comparison Of Integration Cases Of Npp-htsepmentioning

confidence: 99%

“…Hydrogen co-production from subcritical water-cooled nuclear power plants in [19]. Thus, energy storage using hydrogen is not simply an option for high-temperature plants, but could be an opportunity even for existing subcritical water-based NPPs including CANDU stations.…”

Section: Comparison Of Integration Cases Of Npp-htsepmentioning

confidence: 99%

Hydrogen Co-Production From Subcritical Water-Cooled Nuclear Power Plants In Canada

GnanapragasamN.

RylandD.

SuppiahS.

2013

AECL Nuclear Review

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Parametric evaluation of large-scale high-temperature electrolysis hydrogen production using different advanced nuclear reactor heat sources

Cited by 21 publications

References 4 publications

An electrochemical model for syngas production by co-electrolysis of H2O and CO2

An electrochemical model for syngas production by co-electrolysis of H2O and CO2

Optimization and Comparison of Direct and Indirect Supercritical Carbon Dioxide Power Plant Cycles for Nuclear Applications

Hydrogen Co-Production From Subcritical Water-Cooled Nuclear Power Plants In Canada

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