Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels

Alvaro Rodríguez-Prieto, Manuel Callejas, Ernesto Primera, Guglielmo Lomonaco and Ana María Camacho
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Alvaro Rodríguez-Prieto: Department of Manufacturing Engineering, Universidad Nacional de Educación a Distancia (UNED), 28040 Madrid, Spain
Manuel Callejas: Department of Industrial Inspection and Technical Assistance, SGS Tecnos, 28042 Madrid, Spain
Ernesto Primera: Department of Applied Statistics, University of Delaware, 531 South College Avenue, Newark, DE 19716, USA
Guglielmo Lomonaco: GeNERG, Dipartimento di Ingegneria Meccanica, TEC Division, Energetica, Gestionale e dei Trasporti (DIME), Università di Genova (UNIGE), Via all’Opera Pia, 15A, 16145 Genoa, Italy
Ana María Camacho: Department of Manufacturing Engineering, Universidad Nacional de Educación a Distancia (UNED), 28040 Madrid, Spain

Mathematics, 2022, vol. 10, issue 10, 1-17

Abstract: 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.

Keywords: prognosis; design-for-reliability; failure assessment diagram (FAD); pressure vessel; nuclear industry; irradiation embrittlement; analytical prediction model (search for similar items in EconPapers)
JEL-codes: C (search for similar items in EconPapers)
Date: 2022
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