React-compact: a computer code for modeling graphite corrosion and fuel hydrolysis - 18526
Creators
- 1. Ultra Safe Nuclear Corporation 10383 Caminito Banyon, San Diego, CA 92131, USA (United States)
Description
REACT-COMPACT is used to estimate localized graphite corrosion, fuel compact corrosion, and fuel hydrolysis by water vapor for a unit cell geometry within a High Temperature Gas Cooled Reactor (HTGR) fuel block. REACT-COMPACT may also be used to model corrosion in regions with graphite only, including core support posts. REACT-COMPACT solves the species-conservation equation for water vapor in a porous carbon medium for cylindrical geometry. Boundary-layer mass transfer from a helium coolant is modeled at either the inner or outer radius. Within the porous carbon medium, both diffusive and convective transport mechanisms are modeled. The reaction of water vapor with carbonaceous materials is modeled according to a Langmuir-Hinshelwood mechanism. The fuel hydrolysis reaction rate is based on a semi-empirical model derived from experimental data. Model parameters, including densities, void fractions, burn off factors for the intrinsic reaction rates, and diffusivity of water vapor in porous carbon, are evaluated as functions of local burn off. The effects of void-fraction gradients on transport processes are also modeled. REACT-COMPACT also solves the mass conservation equations for reacting fuel and carbonaceous materials, which are coupled in a nonlinear manner to the water-vapor conservation equation because of burn off effects. For this reason, a numerical finite-difference solution is used. This paper describes the theoretical basis for REACT-COMPACT and results for sample problems under representative HTGR conditions. (author)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 10 p.
Conference
- Title
- International Topical Meeting on High Temperature Reactor Technology
- Acronym
- HTR 2016
- Dates
- 6-10 Nov 2016
- Place
- Las Vegas, NV (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52073040
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOUNDARY LAYERS; CARBONACEOUS MATERIALS; COMPUTERIZED SIMULATION; COOLANTS; CORROSION; CYLINDRICAL CONFIGURATION; DENSITY; GEOMETRY; GRAPHITE; HELIUM; HTGR TYPE REACTORS; HYDROLYSIS; MASS TRANSFER; NUCLEAR FUELS; POROUS MATERIALS; REACTION KINETICS; VOID FRACTION; WATER VAPOR
- Descriptors DEC
- CARBON; CHEMICAL REACTIONS; CONFIGURATION; DECOMPOSITION; ELEMENTS; ENERGY SOURCES; FLUIDS; FUELS; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; KINETICS; LAYERS; LYSIS; MATERIALS; MATHEMATICS; MINERALS; NONMETALS; PHYSICAL PROPERTIES; RARE GASES; REACTOR MATERIALS; REACTORS; SIMULATION; SOLVOLYSIS; VAPORS
Optional Information
- Notes
- 13 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)