New observations on the crack growth rate of low alloy nuclear grade ferritic steels under constant active load in oxygenated high-temperature water

Kußmaul, K.; Blind, D.; Läpple, V.

doi:10.1016/s0029-5493(96)01356-8

Cited by 28 publications

(15 citation statements)

References 9 publications

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“…The convective term, however, is not sufficient to keep the crack advance and the crack will arrest in a limited period of time. This observation was made by finite element calculations [90], and supported by a number of recent experimental reports [89,[91][92][93][94]. It is emphasized in all these studies, that an active load application is a vital prerequisite for continuous crack growth.…”

Section: A Step-wise Crack Advance Mechanismsupporting

confidence: 58%

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Fundamental Understanding of Crack Growth in Structural Components of Generation IV Supercritical Light Water Reactors

Balachov¹,

Kobayashi²,

Tanzella³

et al. 2004

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REPORT DOCUMENTATION PAGEForm Approved OMB NO. Public Reporting burden for this collection of information is estimated to average 1 hour per response, including the time for reviewing instructions, searching existing data sources, gathering and maintaining the data needed, and completing and reviewing the collection of information. Send comment regarding this burden estimates or any other aspect of this collection of information, including suggestions for reducing this burden, to Washington Headquarters Services, Directorate for information Operations and Reports, 1215 Jefferson Davis Highway, Suite 1204, Arlington, VA 22202-4302, and This work contributes to the design of safe and economical Generation-IV Super-Critical Water Reactors (SCWRs) by providing a basis for selecting structural materials to ensure the functionality of in-vessel components during the entire service life. During the second year of the project, we completed electrochemical characterization of the oxide film properties and investigation of crack initiation and propagation for candidate structural materials steels under supercritical conditions. We ranked candidate alloys against their susceptibility to environmentally assisted degradation based on the in situ data measured with an SRI-designed controlled distance electrochemistry (CDE) arrangement. A correlation between measurable oxide film properties and susceptibility of austenitic steels to environmentally assisted degradation was observed experimentally. One of the major practical results of the present work is the experimentally proven ability of the economical CDE technique to supply in situ data for ranking candidate structural materials for Generation-IV SCWRs. A potential use of the CDE arrangement developed at SRI for building in situ sensors for monitoring water chemistry in the heat transport circuit of Generation-IV SCWRs was evaluated and proved to be feasible. Understanding basic phenomena. Kinetic parameters of the charge and mass transport processes in the metal/oxide film/supercritical water system are derived from in situ oxide film studies to understand and quantify the rate-controlling processes and, eventually, the fundamentals of the metal oxidation phenomenon at supercritical temperatures. Providing a basis for the development of new alloys. Integration of the in situexperimental information on oxide film resistance to charge and mass transport for alloys of various compositions, along with fracture surface analysis and current theoretical understanding of the relationship between properties of the oxide films and stability of materials, is expected to aid in material selection and the development process. It will do so by providing recommendations for chemical compositions of the alloys in regard to their expected locations in the reactor (or more specifically, in regard to local temperature and oxidizing conditions). 1 WORK PERFORMED AND PRELIMINARY RESULTSDuring this project, SRI completed the electrochemical characterization of the oxide film prop...

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Section: A Step-wise Crack Advance Mechanismsupporting

confidence: 58%

“…A compilation of such data may be found in [89]. The compilation reveals a tremendous scatter, up to five orders of magnitude, in the measured crack growth rates for the same applied loads.…”

Section: Role Of Repassivation In Crack Evolutionmentioning

confidence: 99%

Fundamental Understanding of Crack Growth in Structural Components of Generation IV Supercritical Light Water Reactors

Balachov¹,

Kobayashi²,

Tanzella³

et al. 2004

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show abstract

“…Based on the results of recent SCC tests under simulated BWR conditions [11][12][13]15] and the critical review of older literature data and the field experience, disposition lines for SCC crack growth in LAS during BWR power operation were proposed by an international group of experts, working within the framework of the 'BWRVIP project' of the Electric Power Research Institute (EPRI), and accepted by the US Nuclear Regulatory Commission (NRC) as an interim position (Fig. 3) [13].…”

Section: Bwrvip-60 Scc Disposition Linesmentioning

confidence: 99%

“…The investigations on temperature effects (see Section 4.3.2) clearly revealed a relevant effect of DSA on SCC crack growth in LAS at intermediate temperatures (180-270°C), which even seemed to dominate steel sulphur effects [10,12]. The effect of DSA on SCC is exemplarily illustrated in Figs.…”

Section: Effect Of Dynamic Strain Ageingmentioning

confidence: 99%

“…Notwithstanding the absence of SCC in RPVs in the field, it has been observed in laboratory tests under simulated BWR conditions with crack growth rates (CGR) ranging from 30 lm/year to 3 m/year under nominally similar testing conditions [11][12][13][14][15]. The SCC behaviour of LAS in oxygenated, high-temperature water and its relevance to BWR power operation, in particular its possible effect on both RPV structural integrity and safety, has therefore been a subject of controversial discussions for many years.…”

Section: Introductionmentioning

confidence: 99%

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