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Main Author: Carolina Della Ricco Figueiredo
Format: Artículo científico
Language:en
Published: Sociedade Brasileira de Proteção Radiológica - SBPR 2020
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Online Access:https://www.redalyc.org/articulo.oa?id=722280924039
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author Carolina Della Ricco Figueiredo
author_facet Carolina Della Ricco Figueiredo
contents Recommendation for linearization procedure in nuclear pressure vessel-nozzle intersections Carolina Della Ricco Figueiredo Miguel Mattar Neto Biología design by analysis stress linearization Elastic stress analysis nuclear pressure vessel The pressure vessel design is a fundamental step during the construction of new pressurized water reactors (PWRs). In these facilities, several safety requirements are necessary to guarantee the protection of workers, community and environment against the release of radioactive materials. The Design by Analysis is the procedure presented in the ASME Code, Section III, for nuclear components, which consist of rigorous analysis and classification of all types of stresses and loading conditions to incorporate smaller safety factors increasing the general safety. The limits presented in the ASME Code, Section III, were based on the shell theory. However, precise rules for achieving the various stress categories, in solid finite element analysis, have not been implemented yet in the code. For this reason, this work presents a methodology for the linearization procedure of elastic stresses in pressure vessel-nozzle intersections. Therefore, a vessel was modelled in tridimensional solid finite elements, analyzed and verified as a nuclear component. Then, a discussion of how to perform the code verifications was presented, as well as a mapping of stresses. The lines that were constructed in pressure vessel between transition and structural elements in the longitudinal plane (0º) and lines in structural elements in the nozzle in the transversal plane (90º) present higher stresses and are compared with the ASME Code, Section III limits. 2020 artículo científico 2319-0612 https://www.redalyc.org/articulo.oa?id=722280924039 en http://www.redalyc.org/revista.oa?id=7222 Brazilian Journal of Radiation Sciences application/pdf Sociedade Brasileira de Proteção Radiológica - SBPR Brazilian Journal of Radiation Sciences (Brasil) Num.3A Vol.8
format Artículo científico
id redalyc_722280924039
language en
publishDate 2020
publisher Sociedade Brasileira de Proteção Radiológica - SBPR
spellingShingle Recommendation for linearization procedure in nuclear pressure vessel-nozzle intersections
Carolina Della Ricco Figueiredo
Biología
design by analysis
stress linearization
Elastic stress analysis
nuclear pressure vessel
Recommendation for linearization procedure in nuclear pressure vessel-nozzle intersections Carolina Della Ricco Figueiredo Miguel Mattar Neto Biología design by analysis stress linearization Elastic stress analysis nuclear pressure vessel The pressure vessel design is a fundamental step during the construction of new pressurized water reactors (PWRs). In these facilities, several safety requirements are necessary to guarantee the protection of workers, community and environment against the release of radioactive materials. The Design by Analysis is the procedure presented in the ASME Code, Section III, for nuclear components, which consist of rigorous analysis and classification of all types of stresses and loading conditions to incorporate smaller safety factors increasing the general safety. The limits presented in the ASME Code, Section III, were based on the shell theory. However, precise rules for achieving the various stress categories, in solid finite element analysis, have not been implemented yet in the code. For this reason, this work presents a methodology for the linearization procedure of elastic stresses in pressure vessel-nozzle intersections. Therefore, a vessel was modelled in tridimensional solid finite elements, analyzed and verified as a nuclear component. Then, a discussion of how to perform the code verifications was presented, as well as a mapping of stresses. The lines that were constructed in pressure vessel between transition and structural elements in the longitudinal plane (0º) and lines in structural elements in the nozzle in the transversal plane (90º) present higher stresses and are compared with the ASME Code, Section III limits. 2020 artículo científico 2319-0612 https://www.redalyc.org/articulo.oa?id=722280924039 en http://www.redalyc.org/revista.oa?id=7222 Brazilian Journal of Radiation Sciences application/pdf Sociedade Brasileira de Proteção Radiológica - SBPR Brazilian Journal of Radiation Sciences (Brasil) Num.3A Vol.8
title Recommendation for linearization procedure in nuclear pressure vessel-nozzle intersections
topic Biología
design by analysis
stress linearization
Elastic stress analysis
nuclear pressure vessel
url https://www.redalyc.org/articulo.oa?id=722280924039