Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels
The aim of this work is to present a new analytical model to evaluate jointly the mechanical integrity and the fitness-for-service of nuclear reactor pressure-vessels steels. This new methodology integrates a robust and regulated irradiation embrittlement prediction model such as the ASTM E-900 with...
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| Format: | Article |
| Language: | English |
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MDPI AG
2022-05-01
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| Series: | Mathematics |
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| Online Access: | https://www.mdpi.com/2227-7390/10/10/1779 |
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| author | Alvaro Rodríguez-Prieto Manuel Callejas Ernesto Primera Guglielmo Lomonaco Ana María Camacho |
| author_facet | Alvaro Rodríguez-Prieto Manuel Callejas Ernesto Primera Guglielmo Lomonaco Ana María Camacho |
| author_sort | Alvaro Rodríguez-Prieto |
| collection | DOAJ |
| description | The aim of this work is to present a new analytical model to evaluate jointly the mechanical integrity and the fitness-for-service of nuclear reactor pressure-vessels steels. This new methodology integrates a robust and regulated irradiation embrittlement prediction model such as the ASTM E-900 with the ASME Fitness-for-Service code used widely in other demanding industries, such as oil and gas, to evaluate, among others, the risk of experiencing degradation mechanisms such as the brittle fracture (generated, in this case, due to the irradiation embrittlement). This multicriteria analytical model, which is based on a new formulation of the brittle fracture criterion, allows an adequate prediction of the irradiation effect on the fracture toughness of reactor pressure-vessel steels, letting us jointly evaluate the mechanical integrity and the fitness-for-service of the vessel by using standardized limit conditions. This allows making decisions during the design, manufacturing and in-service of reactor pressure vessels. The results obtained by the application of the methodology are coherent with several historical experimental works. |
| first_indexed | 2024-03-10T03:27:47Z |
| format | Article |
| id | doaj.art-3e1820175a6a4e94a74e280dced49e3f |
| institution | Directory Open Access Journal |
| issn | 2227-7390 |
| language | English |
| last_indexed | 2024-03-10T03:27:47Z |
| publishDate | 2022-05-01 |
| publisher | MDPI AG |
| record_format | Article |
| series | Mathematics |
| spelling | doaj.art-3e1820175a6a4e94a74e280dced49e3f2023-11-23T12:02:19ZengMDPI AGMathematics2227-73902022-05-011010177910.3390/math10101779Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled SteelsAlvaro Rodríguez-Prieto0Manuel Callejas1Ernesto Primera2Guglielmo Lomonaco3Ana María Camacho4Department of Manufacturing Engineering, Universidad Nacional de Educación a Distancia (UNED), 28040 Madrid, SpainDepartment of Industrial Inspection and Technical Assistance, SGS Tecnos, 28042 Madrid, SpainDepartment of Applied Statistics, University of Delaware, 531 South College Avenue, Newark, DE 19716, USAGeNERG, Dipartimento di Ingegneria Meccanica, TEC Division, Energetica, Gestionale e dei Trasporti (DIME), Università di Genova (UNIGE), Via all’Opera Pia, 15A, 16145 Genoa, ItalyDepartment of Manufacturing Engineering, Universidad Nacional de Educación a Distancia (UNED), 28040 Madrid, SpainThe aim of this work is to present a new analytical model to evaluate jointly the mechanical integrity and the fitness-for-service of nuclear reactor pressure-vessels steels. This new methodology integrates a robust and regulated irradiation embrittlement prediction model such as the ASTM E-900 with the ASME Fitness-for-Service code used widely in other demanding industries, such as oil and gas, to evaluate, among others, the risk of experiencing degradation mechanisms such as the brittle fracture (generated, in this case, due to the irradiation embrittlement). This multicriteria analytical model, which is based on a new formulation of the brittle fracture criterion, allows an adequate prediction of the irradiation effect on the fracture toughness of reactor pressure-vessel steels, letting us jointly evaluate the mechanical integrity and the fitness-for-service of the vessel by using standardized limit conditions. This allows making decisions during the design, manufacturing and in-service of reactor pressure vessels. The results obtained by the application of the methodology are coherent with several historical experimental works.https://www.mdpi.com/2227-7390/10/10/1779prognosisdesign-for-reliabilityfailure assessment diagram (FAD)pressure vesselnuclear industryirradiation embrittlement |
| spellingShingle | Alvaro Rodríguez-Prieto Manuel Callejas Ernesto Primera Guglielmo Lomonaco Ana María Camacho Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels Mathematics prognosis design-for-reliability failure assessment diagram (FAD) pressure vessel nuclear industry irradiation embrittlement |
| title | Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels |
| title_full | Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels |
| title_fullStr | Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels |
| title_full_unstemmed | Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels |
| title_short | Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels |
| title_sort | multicriteria analytical model for mechanical integrity prognostics of reactor pressure vessels manufactured from forged and rolled steels |
| topic | prognosis design-for-reliability failure assessment diagram (FAD) pressure vessel nuclear industry irradiation embrittlement |
| url | https://www.mdpi.com/2227-7390/10/10/1779 |
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