Published 1982
| Version v1
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Fuel rod behavior of a PWR during load following
Description
The behavior of a PWR fuel rod when operating in normal power cycles, excluding in case of accidents, is analysed. A computer code, that makes the mechanical analysis of the cladding using the finite element method was developed. The ramps and power cycles were simulated suposing the existence of cracks in pellets when the cladding-pellet interaction are done. As a result, an operation procedure of the fuel rod in power cycle is recommended. (E.G.)
Abstract (Portuguese)
E analisado o comportamento da barra combustivel de um reator nuclear PWR quando operando em ciclos normais de potencia excluindo-se casos de acidentes. Foi desenvolvido um codigo cujo objetivo principal e a analise mecanica do revestimento empregando para tal o metodo de elemento finito. Foram simuladas rampas e ciclos de potencia supondo a existencia de rachaduras na pastilha quando da interacao pastilha-revestimento. Como resultado do estudo, recomenda-se um procedimento de operacao da barra combustivel em ciclos de potencia. (Autor)Files
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Additional details
Additional titles
- Original title (Portuguese)
- Comportamento da barra combustivel de um reator tipo PWR em seguimento de carga
Publishing Information
- Imprint Title
- 3. National Meeting of Reactor Physics
- Imprint Pagination
- 570 p.
- Journal Page Range
- p. 368-376.
- Report number
- INIS-BR--95
Conference
- Title
- 3. National Meeting of Reactor Physics.
- Dates
- 12-14 Dec 1982.
- Place
- Itaipava, RJ (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 14807158
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; FINITE ELEMENT METHOD; FUEL RODS; PWR TYPE REACTORS; ZIRCALOY
- Descriptors DEC
- ALLOYS; DEPOSITION; FUEL ELEMENTS; NUMERICAL SOLUTION; REACTOR COMPONENTS; REACTORS; SURFACE COATING; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- Imprint:3. Encontro Nacional de Fisica de Reatores.