Natural convection effects during a severe accident
Creators
- 1. Area de Ingenieria en Recursos Energeticos, Universidad Autonoma Metropolitana-Iztapalapa, Mexico, D.F. (Mexico)
- 2. Departamento de Sistemas Energeticos, Universidad Nacional Autonoma de Mexico, Mexico, D.F. (Mexico)
Description
The aim of this work is to study the behavior of natural convection effects on the temporal evolution of the distributions of hydrogen concentration and temperature profiles in a fuel assembly where a stream of steam is flowing. The analysis considers the fuel element without mitigation effects. The mass transfer phenomenon considers that the hydrogen generated diffuses in the steam by convection and diffusion. Oxidation of the cladding, rods, and other components in the core constructed in zirconium base alloy by steam is a critical issue in LWR accident producing severe core damage. The oxygen consumed by the zirconium is supplied by the up flow of steam from the water pool below the uncovered core, supplemented in the case of PWR by gas recirculation from the cooler outer regions of the core to hotter zones. Fuel rod cladding oxidation is then one of the key phenomena influencing the core behavior under high-temperature accident conditions. The chemical reaction of oxidation is highly exothermic, which determines the hydrogen rate generation and the cladding brittleness and degradation. The heat transfer process in the fuel assembly is considered with a reduced order model. The Boussinesq approximation was applied in the momentum equations for multicomponent flow analysis that considers natural convection due to buoyancy forces, which is related with thermal and hydrogen concentration effects. The heat transfer processes are coupled with the mass transfer process through the reaction rate and heat reaction at the interface, which are functions of the temperature. Additionally, the hydraulic process is highly coupled with the heat and mass transfer processes through the convective and buoyancy forces. In this sense, the simultaneous transfer of heat, mass and momentum are considered in this work. The numerical simulation was carried out in an averaging channel that represents a core reactor with the fuel rod with its gap and cladding and cooling steam of a BWR. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)
- Imprint Pagination
- 2846 p.
- Journal Page Range
- 13 p.
Conference
- Title
- 10. international topical meeting on nuclear thermal hydraulics, operation and safety
- Acronym
- NUTHOS-10
- Dates
- 14-18 Dec 2014
- Place
- Ginowan, Okinawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47070571
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COOLANT LOOPS; FUEL ASSEMBLIES; FUEL RODS; HYDROGEN; NATURAL CONVECTION; NUMERICAL SOLUTION; OXIDATION; PRESSURE DROP; REACTOR CORE DISRUPTION; REACTOR CORES; TEMPERATURE DISTRIBUTION; WATER COOLED REACTORS; ZIRCONIUM
- Descriptors DEC
- ACCIDENTS; CHEMICAL REACTIONS; CONVECTION; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; ENERGY TRANSFER; FUEL ELEMENTS; HEAT TRANSFER; MASS TRANSFER; MATHEMATICAL SOLUTIONS; METALS; NONMETALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; TRANSITION ELEMENTS
Optional Information
- Notes
- Available as USB Flash Memory Data in PDF format. Paper ID: NUTHOS10-1101.pdf; 25 refs., 6 figs.