Modeling a filter press electrolyzer by using two coupled codes within nuclear gen.IV hydrogen production
- Commissariat a l'Energie Atomique CEA/DEN/VRH/DTEC BP 17171 30207 Bagnols-sur-Ceze Cedex (France)
- ASTEK RHONE-ALPES, 1 Place du verseau 38130 Echirolles (France)
- Laboratoire EPM, Madylam 1340 Rue de la Piscine Domaine Univ. 38400 Saint Martin d'Heres (France)
- LEPMI, ENSEEG 1130 Rue de la Piscine 38402 Saint Martin d'Heres (France)
Mass production of hydrogen is a major issue for the coming decades particularly to decrease greenhouse gas production. The development of fourth-generation high temperature nuclear reactors has led to renewed interest for hydrogen production. In France, the CEA is investigating new processes using nuclear reactors such as the Westinghouse hybrid cycle. A recent study was devoted to electrical modeling of the hydrogen electrolyzer, which is the key unit of this process. An extensive literature review led to the choice of electrolyte and electrode materials, and the preliminary design of a new cell for production of hydrogen was evaluated. This paper describes an improved model coupling the electrical and thermal phenomena with hydrodynamics in the electrolyzer. The hydrogen electrolyzer chosen here is a filter press design comprising a stack of cathode and anode compartments separated by a membrane. Hydrogen is reduced at the cathode and SO{sub 2} is oxidized at the anode. In a complex reactor of this type the main coupled physical phenomena involved are forced convection of the electrolyte flows, a plume of hydrogen bubbles that modifies the local electrolyte conductivity, and irreversible processes (Joule effect, over-potentials, etc.) that contribute to local overheating. The secondary current distribution was modeled with a commercial FEM code, Flux Expert{sup R}, which was customized with specific finite interfacial elements capable of describing the potential discontinuity associated with the electrochemical over-potential. Since the finite-element method is not capable of properly describing the complex two-phase flows in the cathode compartment, the Fluent{sup R} CFD code was used for thermohydraulic computations. In this way each physical phenomenon was modeled using the best numerical method. The coupling implements an iterative process in which each code computes the physical data it has to transmit to the other one: the two-phase thermohydraulic problem is solved by Fluent{sup R} using the Flux Expert{sup R} current density and heat sources; the secondary distribution and heat losses are solved by Flux Expert{sup R} using Fluent{sup R} temperature field and flow velocities. The computations use two different meshes and interpolations from one mesh to the other require a 3D algorithm to localize the calculation points. A set of dedicated library routines was developed for process initiation, message passing, and synchronization of the two codes. The first results obtained with the two coupled commercial codes give realistic distributions for electrical current density, gas fraction and velocity in the electrolyzer. A design optimization phase is in progress before proceeding to the final design and manufacturing of a pilot electrolyzer. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 20979638
- Resource Relation:
- Conference: Advanced nuclear fuel cycles and systems (GLOBAL 2007), Boise - Idaho (United States), 9-13 Sep 2007; Other Information: Country of input: France; 8 refs; Related Information: In: Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems, 1873 pages.
- Country of Publication:
- United States
- Language:
- English
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