Published 1985
| Version v1
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Simulation of thermal behavior of nuclear fuel rod by electrically heated pin
- 1. Centro Tecnico Aeroespacial, Sao Jose dos Campos (Brazil). Inst. Tecnologico de Aeronautica
Description
The utilization of electrically heated rods for the simulation of nuclear fuel rods represents an universally adopted method by the nuclear industry to study thermalhydraulic problems. The present work represents the development of a method to obtain the time variation of the electric linear power necessary to simulate a given nuclear power transient in order to yield the same temperature and heat flux conditions in the surface of the electrical heater that would be obtained by the nuclear fuel rod. (Author)
Abstract (Portuguese)
A utilizacao de barras aquecidas electricamente para simulacao de barras de combustiveis nucleares representa um metodo universalmente adotado pela industria nuclear para estudar problemas termohidraulicos. Apresenta-se o desenvolvimento de um metodo para obter a variacao de tempo da potencia eletrica linear necessaria para simular um dado transiente de potencia nuclear que concorde com as mesmas condicoes de temperatura e fluxo de calor na superficie do aquecedor eletrico e com as que serao obtidas pela barra de combustivel nuclear. (E.G.)Files
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Additional details
Publishing Information
- Imprint Pagination
- 4 p.
- Report number
- INIS-BR--916
Conference
- Title
- 8. Brazilian Congress on Mechanical Engineering.
- Dates
- 10-13 Dec 1985.
- Place
- Sao Jose dos Campos, SP (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 19023751
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL RODS; HEAT TRANSFER; NUCLEAR FUELS; PWR TYPE REACTORS; SIMULATION; TRANSIENTS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY SOURCES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; MATERIALS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS