Published 1985
| Version v1
Miscellaneous
Open
Analysis of nuclear reactor pressure vessel flanges
Creators
- 1. Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo (Brazil)
Description
This work proposes a methodology for the structural analysis of high diameter nuclear reactor pressure vessel flanges. In the analysis the vessel is divided into shell-of-revolution elements, the flanges are represented by rigid rings, and the bolts are treated as beams. The flexibility method is used for solving the problem, and the results are compared with results obtained by the finite element method. (Author)
Abstract (Portuguese)
Neste trabalho e proposta uma metodologia para a analise estrutural de flanges de grande diametro utilizados em vasos de pressao de reatores nucleares. Nesta analise o vaso e dividido em elementos de casca de revolucao, os flanges sao representados por aneis rigidos e os parafusos sao tratados como vigas. Utiliza-se o metodo dos esforcos para a solucao do problema, sendo que os resultados calculados sao comparados com resultados obtidos pelo metodo dos elementos finitos. (Autor)Files
18052325.pdf
Files
(167.9 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:23fd72421693feb731e557eeef4ba242
|
167.9 kB | Preview Download |
Additional details
Additional titles
- Original title (Portuguese)
- Analise de flanges de vasos de pressao nucleares
Publishing Information
- Imprint Pagination
- 4 p.
- Report number
- INIS-BR--615
Conference
- Title
- 8. Brazilian Congress of Mechanical Engineering.
- Dates
- Dec 1985.
- Place
- Sao Jose dos Campos, SP (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 18052325
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANGRA-1 REACTOR; COMPARATIVE EVALUATIONS; FINITE ELEMENT METHOD; FLANGES; FLEXIBILITY; MECHANICAL STRUCTURES; NUCLEAR POWER PLANTS; PRESSURE VESSELS
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; EVALUATION; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; NUMERICAL SOLUTION; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; TENSILE PROPERTIES; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS