Evaluation of ???Safety Related??? and ???Important to Safety??? terminology for safety classification of nuclear installation items in Brazil

dc.creatorBARONI, D.B.
dc.creatorBORSOI, S.S.
dc.creatorMATTAR NETO, M.
dc.creatorOLIVEIRA, P.S.P.
dc.creatorMATURANA, M.C.
dc.date2022
dc.date2022-12-19T18:28:02Z
dc.date2022-12-19T18:28:02Z
dc.date.accessioned2023-09-28T14:23:56Z
dc.date.available2023-09-28T14:23:56Z
dc.identifier2319-0612
dc.identifierhttp://repositorio.ipen.br/handle/123456789/33482
dc.identifier3A
dc.identifier10
dc.identifier10.15392/2319-0612.2022.1960
dc.identifier0000-0002-2295-1021
dc.identifierSem Percentil
dc.identifierSem Percentil CiteScore
dc.identifier.urihttps://repositorioslatinoamericanos.uchile.cl/handle/2250/9003701
dc.descriptionIn general terms, safety demonstration of nuclear installations is carried out through an assessment of compliance with design criteria and safety requirements established in national and international codes and standards applicable to each type of installation. In addition, a safety analysis consisting of installation behavior study during its useful lifetime, shall be developed considering normal operating conditions, transients, and postulated accidents, to determine safety margins and verify the adequacy of items designed to prevent accidents or mitigate their consequences. Also, design requirements applicable to each installation item depend on its classification with respect to safety. Thus, safety classification of structures, systems, and components (SSCs) must be performed based on adequate methods and clear and consistent criteria to ensure that an overall safety level expected for the installation is achieved. It is worth emphasizing the importance of the terminology adopted and the understanding of concepts definitions used in a safety classification process. The objective of this paper is to present a review of the application of ???safety related item??? and ???item important to safety??? terminology, evaluating definitions and interpretations given by the International Atomic Energy Agency (IAEA), the United States Nuclear Regulatory Commission (U.S.NRC) and the National Nuclear Energy Commission (CNEN) of Brazil. In this work, this subject is raised to demonstrate that divergent definitions and misinterpretations of concepts may result in inconsistencies in SSCs safety classification.
dc.format1-17
dc.relationBrazilian Journal of Radiation Sciences
dc.rightsopenAccess
dc.sourceMeeting on Nuclear Reactor Physics and Thermal hydraulics (ENFIR), 22nd; Meeting on Nuclear Industry (ENIN), 7th, November 29 - December 2, 2021, Online
dc.subjectNUCLEAR FACILITIES
dc.subjectRADIATION PROTECTION
dc.subjectSAFETY STANDARDS
dc.subjectACCIDENTS
dc.subjectBRAZIL
dc.titleEvaluation of ???Safety Related??? and ???Important to Safety??? terminology for safety classification of nuclear installation items in Brazil
dc.typeArtigo de peri??dico
dc.coverageN


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