Reliability-Based Evaluation of the Suitability of Polymers for Additive Manufacturing Intended for Extreme Operating Conditions

Rodríguez-Prieto, Álvaro; Primera, Ernesto; Callejas, Manuel; Camacho, Ana María

doi:10.3390/polym12102327

Cited by 2 publications

(4 citation statements)

References 54 publications

(50 reference statements)

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“…Using an exponential distribution for the degradation (according to the Arrhenius model), the reliability function R ( t ) can be calculated [ 24 ] according to Equation (6).

where λ is the failure rate, calculated as

and t , the considered time.…”

Section: Resultsmentioning

confidence: 99%

“…This is very reasonable because a hardening found in a recently manufactured O-rings probably implies a defective mechanical integrity or a degraded composition, while the same value for a stored O-ring just indicates that a hardening process took place. On the other hand, probability of failure distribution ( POF ( t )) can be calculated [ 24 ] according to Equation (7).

…”

Section: Resultsmentioning

confidence: 99%

“…Polymers, and especially elastomers, play a key role as part of the many mechanical, electrical, and electronic components found in nuclear power generation plants [ 24 ]. Condition monitoring and an understanding of the degradation processes due to short-term thermal stress have been of interest to the nuclear industry because of qualification requirements [ 25 ].…”

Section: Introductionmentioning

confidence: 99%

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Reliability Prediction of Acrylonitrile O-Ring for Nuclear Power Applications Based on Shore Hardness Measurements

et al. 2021

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The degradation of polymeric components is of considerable interest to the nuclear industry and its regulatory bodies. The objective of this work was the development of a methodology to determine the useful life—based on the storage temperature—of acrylonitrile O-rings used as mechanical sealing elements to prevent leakages in nuclear equipment. To this aim, a reliability-based approach that allows prediction of the use-suitability of different storage scenarios (that involve different storage times and temperatures) considering the further required in-service performance, is presented. Thus, experimental measurements of Shore A hardness have been correlated with storage variables (temperature and storage time). The storage (and its associated hardening) was proved to have a direct effect on in-service durability, reducing this by up to 60.40%. Based on this model, the in-service performance was predicted; after the first three years of operation the increase in probability of failure (POF) was practically insignificant. Nevertheless, from this point on, and especially, from 5 years of operation, the POF increased from 10% to 20% at approximately 6 years (for new and stored). From the study, it was verified that for any of the analysis scenarios, the limit established criterion was above that of the storage time premise considered in usual nuclear industry practices. The novelty of this work is that from a non-destructive test, like a Shore A hardness measurement, the useful life and reliability of O-rings can be estimated and be, accordingly, a decision tool that allows for improvement in the management of maintenance of safety-related equipment. Finally, it was proved that the storage strategies of our nuclear power plants are successful, perfectly meeting the expectations of suitability and functionality of the components when they are installed after storage.

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“…Using an exponential distribution for the degradation (according to the Arrhenius model), the reliability function R ( t ) can be calculated [ 24 ] according to Equation (6).

where λ is the failure rate, calculated as

and t , the considered time.…”

Section: Resultsmentioning

confidence: 99%

…”

Section: Resultsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Reliability Prediction of Acrylonitrile O-Ring for Nuclear Power Applications Based on Shore Hardness Measurements

et al. 2021

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“…The capsules include tensile, Charpy impact and fracture toughness specimens, as well as the instrumentation necessary to monitor neutron fluence and temperature [8]. Traditional material research relies on a considerable amount of experimental trial designs, which are time-consuming and costly [39]. There are several consolidated prediction models to estimate the ∆RT DBT in irradiated RPV steels; these are mainly the NUREG/CR-6551 [40] and ASTM E-900 [41].…”

Section: Introductionmentioning

confidence: 99%

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

Rodríguez-Prieto

Callejas²,

Primera

et al. 2022

Mathematics

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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.

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Reliability-Based Evaluation of the Suitability of Polymers for Additive Manufacturing Intended for Extreme Operating Conditions

Cited by 2 publications

References 54 publications

Reliability Prediction of Acrylonitrile O-Ring for Nuclear Power Applications Based on Shore Hardness Measurements

Reliability Prediction of Acrylonitrile O-Ring for Nuclear Power Applications Based on Shore Hardness Measurements

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

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