ISSN: 1945-7553
CODEN: JTEVAB
Published Online: 10 August 2011
Page Count: 10

Evaluation of the ASTM and ISO J Initiation Procedures by Applying the Unloading Compliance Technique to Reactor Pressure Vessel Steels

Arora, Kanwer Singh
Institute of Safety Research,

Viehrig, Hans Werner
Institute of Safety Research,

(Received 24 September 2010; accepted 18 May 2011)

Abstract

Other than the brittle failure, the ductile behavior of the aged nuclear reactor pressure vessel (RPV) steels is also of interest for the integrity assessment and evaluation of the irradiation response. The fracture toughness of high toughness materials like RPV steels can be characterized by a J-R curve. Since the RPV steel material available for testing purposes, like surveillance specimens, is limited, the single specimen method is used for the J-R curve determination. In this study, J-R curves were measured on Charpy size SE(B) and 1T-C(T) specimens of different RPV steels in the unirradiated and irradiated conditions. It was observed that despite the available sophisticated instrumentation and strict implementation of the recommended test procedures, the J-initiation value for all the different material specimens tested could not be ascertained according to the test standards ASTM E1820 and ISO 12 135. For Charpy size SE(B) specimens, it was found that though valid J_IC/J_0.2BL values could be obtained in irradiated conditions, in un-irradiated conditions, especially for high toughness RPV steels, it was not possible. The evaluation showed that the a_oq fit of the ASTM standard compensates uncertainties in the initial J-Δa value resulting in reliable and more number of qualified test results. But these uncertainties strongly influence the A parameters of the ISO fit and the J_0.2BL(B) value. Additionally, in the ISO evaluation the lower offset of the first exclusion line and a higher slope results in lower J_0.2BL values compared to the ASTM analysis. Furthermore, for the two specimen geometries the course of J-R curves up to the J_Q value was similar even for high toughness materials, but the lower specimen size was disqualified due to the lower prescribed J_limit. Similarly, the J-R curves for un-irradiated and irradiated condition had a similar course up to the J_0.2BL value, even for extremely high irradiation induced embrittlement.

Keywords:
fracture toughness, ductile tearing, J-R curve, single specimen approach, unloading compliance, ASTM E1820, ISO 12 135, reactor pressure vessel steels

Paper ID: JTE103405
DOI: 10.1520/JTE103405
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