Using of SPT method for estimation of mechanical properties changes of RPV steels after irradiation in the Halden reactor

Adamech, Marek; Petzová, Jana; Březina, Martin; Kapusňák, Michal

doi:10.5334/uproc.2

Cited by 2 publications

(6 citation statements)

References 1 publication

(1 reference statement)

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“…The graphical demonstration of the changes that occurred as a result of neutron irradiation is given in Figures 5 and 6. It can be seen from the figures that after the irradiation, the strength characteristics of all the evaluated materials slightly increased [5]. Table 1.…”

Section: Resultsmentioning

confidence: 87%

“…The transition temperature of ferritic steels rises with increasing irradiation level. For austenitic steel 08Ch18N10T in contrast there is no transition temperature and no effect of the irradiation; the SPT energy decreases with increasing temperature [5]. Table 2.…”

Section: Resultsmentioning

confidence: 99%

“…Table 1. Tensile properties evaluated using SPT tests before and after irradiation of R 4BZ3 chain [5]. The DBTTSPT transition temperature values determined by the SPT test for ferritic materials are summarized in Table 2.…”

Section: Resultsmentioning

confidence: 99%

“…The design of irradiation chains, measuring of irradiation temperature and neutron fluence is based on the experience from the realized surveillance specimen programs. The innovations in this project are [5]:…”

Section: Experimental Materialsmentioning

confidence: 99%

“…Underclad HAZ-II of the RPV -24.6 50.Transversely-orientated underclad HAZ from the RPV -(a) Rise in DBTTSPT of HAZ I.; (b) Rise in DBTTSPT of HAZ II [5]…”

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confidence: 99%

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Interim results of the reactor pressure vessel materials evaluation within the framework of the implemented Advanced Surveillance Specimen Programme

Kapusňák

Petzová²,

Březina

et al. 2018

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The reactor pressure vessel (RPV) is the most critical component of every nuclear power plant (NPP) and continuous evaluation of its mechanical properties is a necessity for long and safe operation. Standard tests require a collection of large-dimension samples coming from the precious and archive materials, usually produced as control segments. Since SPT testing samples are quite small, high activity of irradiated materials is no longer an issue. The SPT technique therefore represents a very useful and effective method applied for characterization of mechanical properties such as ultimate tensile strength (Rm), yield strength (Re), and fracture appearance transition temperature (FATT). Monitoring of structural components in nuclear power plants receives much attention, particularly, in the context of long term operation (LTO) of current plants where the amount of material available for destructive testing is considerably limited.

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Section: Resultsmentioning

confidence: 87%

Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

Section: Experimental Materialsmentioning

confidence: 99%

“…Underclad HAZ-II of the RPV -24.6 50.Transversely-orientated underclad HAZ from the RPV -(a) Rise in DBTTSPT of HAZ I.; (b) Rise in DBTTSPT of HAZ II [5]…”

mentioning

confidence: 99%

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Interim results of the reactor pressure vessel materials evaluation within the framework of the implemented Advanced Surveillance Specimen Programme

Kapusňák

Petzová²,

Březina

et al. 2018

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Mechanics of the small punch test: a review and qualification of additive manufacturing materials

Torres

Gordon

2021

J Mater Sci

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The small punch test (SPT) was developed for situations where source material is scarce, costly or otherwise difficult to acquire, and has been used for assessing components with variable, location-dependent material properties. Although lacking standardization, the SPT has been employed to assess material properties and verified using traditional testing. Several methods exist for equating SPT results with traditional stress–strain data. There are, however, areas of weakness, such as fracture and fatigue approaches. This document outlines the history and methodologies of SPT, reviewing the body of contemporary literature and presenting relevant findings and formulations for correlating SPT results with conventional tests. Analysis of literature is extended to evaluating the suitability of the SPT for use with additively manufactured (AM) materials. The suitability of this approach is shown through a parametric study using an approximation of the SPT via FEA, varying material properties as would be seen with varying AM process parameters. Equations describing the relationship between SPT results and conventional testing data are presented. Correlation constants dictating these relationships are determined using an accumulation of data from the literature reviewed here, along with novel experimental data. This includes AM materials to assess the fit of these and provide context for a wider view of the methodology and its interest to materials science and additive manufacturing. A case is made for the continued development of the small punch test, identifying strengths and knowledge gaps, showing need for standardization of this simple yet highly versatile method for expediting studies of material properties and optimization.

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Using of SPT method for estimation of mechanical properties changes of RPV steels after irradiation in the Halden reactor

Cited by 2 publications

References 1 publication

Interim results of the reactor pressure vessel materials evaluation within the framework of the implemented Advanced Surveillance Specimen Programme

Interim results of the reactor pressure vessel materials evaluation within the framework of the implemented Advanced Surveillance Specimen Programme

Mechanics of the small punch test: a review and qualification of additive manufacturing materials

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