Thermohydraulic Design of the RP-10 Reactor with the Fuel Elements of U3Si2 in Forced Convection
Creators
- 1. Instituto Peruano de Energía Nuclear, Dirección de Producción, Lima (Peru)
- 2. Universidad Nacional del Callao, Facultad de Física, Lima (Peru)
Description
Switching from uranium oxide fuel U3O8 to uranium silicide fuel U3Si2, in the RP-10 nuclear reactor, requires maintaining safety conditions established. The objective of this evaluation was to verify that all safety limits established are met and that the thermohydraulic parameters maintain their values within limits when the reactor is in operation. The calculation model thermohydraulic in forced convection, considers the hydraulic analysis with which determines the flow rate distribution of the coolant in the core and the determination of the velocity of the coolant in each existing channel in the core; later considers the thermal analysis, where the thermal flux is determined for conditions of critical flow, which would cause damage to the structure of the fuel elements, due to For this reason, a safety margin equal to 2 is established. (author)
Availability note (English)
Available on-line: https://revistas.ipen.gob.pe/ict/article/view/147Abstract (Spanish)
El cambio de combustible de óxido de uranio U3O8 por combustible de siliciuro de uranio U3Si2, en el reactor nuclear RP-10, requiere mantener las condiciones de seguridad establecida. El objetivo de esta evaluación fue verificar que todos los límites de seguridad establecidos se cumplen y que los parámetros termohidráulicos mantengan sus valores dentro de los límites cuando el reactor está en operación. El modelo de cálculo termohidráulico en convección forzada, considera el análisis hidráulico con el cual se determina la distribución de flujo de caudal del refrigerante en el núcleo y la determinación de la velocidad del refrigerante en cada canal existente en el núcleo; luego considera el análisis térmico, donde se determina el flujo térmico para condiciones de flujo crítico, el cual produciría daños a la estructura de los elementos combustibles, por esta razón se estable un margen de seguridad igual a 2.Additional details
Additional titles
- Original title (Spanish)
- Diseño Termohidráulico del Reactor RP-10 con los Elementos Combustibles de U3Si2 en Convección Forzada
Identifiers
Publishing Information
- Journal Title
- Informe Cientifico Tecnologico (Online)
- Journal Volume
- 17
- Journal Issue
- 1
- Journal Page Range
- p. 48
- ISSN
- 2225-2029
INIS
- Country of Publication
- Peru
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54012490
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COOLANTS; CRITICAL FLOW; FLOW RATE; FORCED CONVECTION; FUEL ELEMENTS; NUCLEAR FUELS; RP-10 REACTOR; SAFETY MARGINS; THERMAL ANALYSIS; THERMAL HYDRAULICS; URANIUM OXIDES U3O8; URANIUM SILICIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CONVECTION; ENERGY SOURCES; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; FUELS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MATERIALS; MECHANICS; OXIDES; OXYGEN COMPOUNDS; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SILICIDES; SILICON COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Informe Cient#Latin Small Letter I With Acute#fico Tecnol#Latin Small Letter O With Acute#gico is an open access publication distributed under the terms and conditions of the Creative Commons Attribution license (CC BY).