Published 2018 | Version v1
Miscellaneous Open

Evaluation of average temperature for different coatings and fuels

Creators

  • 1. Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Dept. de Engenharia Nuclear

Description

Two types of fuels and three types of coatings are evaluated considering their thermal behavior. The objective is to obtain the average temperature of the different components of the fuel rod to further evaluate the neutron behavior. The Angra-2 core modeled in a previous work on the RELAP5-3D thermohydraulic analysis code was used and the heat transfer properties of the different materials were appropriately modified; then the nucleus was simulated under steady state conditions. The results with the different coatings (FeCrAl and SiC HNS) and different fuels (UO2 and U3Si2), besides their respective combinations, were evaluated and compared with the standard fuel (UO2) and coating (Zirc4). The average temperatures were obtained and will be used in later works to analyze the neutron design

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Additional details

Additional titles

Original title (Portuguese)
Avaliação da temperatura média para diferentes revestimentos e combustíveis

Publishing Information

Imprint Pagination
9 p.
Report number
INIS-BR--22768

Conference

Title
week on nuclear engineering and radiation sciences
Acronym
4. SENCIR 2018
Dates
6-8 Nov 2018
Place
Belo Horizonte, MG (Brazil)

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
50064752
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ANGRA-2 REACTOR; COATINGS; COMPUTERIZED SIMULATION; FUEL RODS; IRON ALLOYS; NUCLEAR FUELS; R CODES; REACTOR CORES; SILICON CARBIDES; STEADY-STATE CONDITIONS; THERMAL ANALYSIS; THERMAL CONDUCTIVITY; ZIRCALOY
Descriptors DEC
ALLOYS; CARBIDES; CARBON COMPOUNDS; COMPUTER CODES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; MATERIALS; PHYSICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SILICON COMPOUNDS; SIMULATION; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS