Published 2014
| Version v1
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Study of heat transfer in 3D fuel rods of the EPRI-9R reactor modified
Creators
- Affonso, Renato Raoni Werneck1
- Lava, Deise Diana1
- Borges, Diogo da Silva1
- Sampaio, Paulo Augusto Berquo de1
- Moreira, Maria de Lourdes1
- Sociedade Brasileira de Protecao Radiologica (SBPR), Recife, PB (Brazil)
- Associacao Brasileira de Ensaios nao Destrutivos e Inspecao (ABENDI), Sao Paulo, SP (Brazil)
- Federacion de Radioproteccion da America Latina y el Caribe (FRALC), Rio de Janeiro, RJ (Brazil)
- 1. Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)
Description
This paper aims to conduct a case study of the fuel rods that have the highest and the lowest average power of the EPRI-9R 3D reactor modified , for various positions of the control rods banks. For this, will be addressed the verification of computer code, comparing the results obtained with analytical solutions. This check is important so that, subsequently, it is possible use the program to understand the behavior of the fuel rods and the coolant channel of the EPRI-9R 3D reactor modified. Thus, in view of the scope of this paper, first a brief introducing on the heat transfer is done, including the rod equations and the equation of energy in the channel to allow the analysis of the results
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46034397.pdf
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Additional details
Additional titles
- Original title (Portuguese)
- Estudo da transferencia de calor em varetas combustiveis 3D do reator EPRI-9R 3D modificado
Publishing Information
- Imprint Pagination
- 11 p.
- Report number
- INIS-BR--14921
Conference
- Title
- International joint conference Radio 2014
- Dates
- 26-29 Aug 2014
- Place
- Gramado, RS (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 46034397
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; COOLANTS; DEPARTURE NUCLEATE BOILING; FINITE ELEMENT METHOD; FUEL PELLETS; FUEL RODS; FUEL-COOLANT INTERACTIONS; HEAT FLUX; HEAT TRANSFER; POWER DISTRIBUTION; PWR TYPE REACTORS; SAFETY ANALYSIS
- Descriptors DEC
- BOILING; CALCULATION METHODS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; MATHEMATICAL SOLUTIONS; NUCLEATE BOILING; NUMERICAL SOLUTION; PELLETS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS