Influence of radiation heat transfer during a severe accident
Creators
- 1. Universidad Autonoma Metropolitana, Unidad Iztapalapa, San Rafael Atlixco No. 186, Col. Vicentina, 09340 Ciudad de Mexico (Mexico)
- 2. Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)
Description
The aim of this work is to determine the influence of the radiation heat transfer on an average fuel channel during a severe accident of a BWR nuclear power plant. The analysis considers the radiation heat transfer in a participating medium, where the gases inside the system participate in the radiation heat transfer. We consider the steam-water mixture as an isothermal gray gas, and the boundaries of the system as a gray diffuse isothermal surface for the clad and refractory surfaces for the rest, and consider the average fuel channel as an enclosure system. During a severe accident, generation and diffusion of hydrogen begin at high temperature range (1,273 to 2,100 K), and the fuel rod cladding oxidation, but the hydrogen generated do not participate in the radiation heat transfer because it does not have any radiation properties. The heat transfer process in the fuel assembly is considered with a reduced order model, and from this, the convection and the radiation heat transfer is introduced in the system. In this paper, a system with and without the radiation heat transfer term was calculated and analyzed in order to obtain the influence of the radiation heat transfer on the average fuel channel. We show the behavior of radiation heat transfer effects on the temporal evolution of the hydrogen concentration and temperature profiles in a fuel assembly, where a stream of steam is flowing. Finally, this study is a practical complement for more accurate modeling of a severe accident analysis. (Author)
Availability note (English)
Available from Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion, 52750 Ocoyoacac, Estado de Mexico (MX), e-mail: mclaudia.gonzalez@inin.gob.mxAdditional details
Publishing Information
- Publisher
- Sociedad Nuclear Mexicana
- Imprint Place
- Ciudad de Mexico (Mexico)
- Imprint Pagination
- 14 p.
Conference
- Title
- nuclear energy, a necessary option; 15. SMSR National Congress: safe use of radiation for better quality of life
- Original Conference Title
- 27. Congreso Anual de la SNM: energia nuclear, una opcion necesaria
- Acronym
- 27. SNM Annual Congress
- Dates
- 3-6 Jul 2016
- Place
- Villahermosa, Tabasco (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 48057403
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; CLADDING; CONCENTRATION RATIO; CONVECTION; DIFFUSION; FUEL ASSEMBLIES; FUEL RODS; GASES; HEAT; HYDROGEN; MIXTURES; NUCLEAR FUELS; NUCLEAR POWER PLANTS; OXIDATION; RADIATION DOSE UNITS; SEVERE ACCIDENTS; STEAM; SURFACES; TEMPERATURE RANGE 0400-1000 K; WATER
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; CHEMICAL REACTIONS; DEPOSITION; DIMENSIONLESS NUMBERS; DISPERSIONS; ELEMENTS; ENERGY; ENERGY SOURCES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUIDS; FUEL ELEMENTS; FUELS; HEAT TRANSFER; HYDROGEN COMPOUNDS; MASS TRANSFER; MATERIALS; NONMETALS; NUCLEAR FACILITIES; OXYGEN COMPOUNDS; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SURFACE COATING; TEMPERATURE RANGE; THERMAL POWER PLANTS; THERMAL REACTORS; UNITS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Funding organization
- GE Hitachi (United States); Toshiba Westinghouse nuclear (United States); GD Energy Services (Spain); Vertek Industrial Supply Inc. (United States); Nukem (Germany); Grupo IAI (Mexico); Tecnatom (Spain); EERMS (Mexico); PetroServicios (Mexico); Control de Radiaciones e Ingenieria, S. A. de C. V. (Mexico)