Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors 1999
DOI: 10.1002/9781118787618.ch90
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Stress Corrosion Cracking of Low Alloy Steels under BWR Conditions; Assessment of Crack Growth Rate Algorithms

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Cited by 5 publications
(4 citation statements)
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“…In the following paragraphs, the adequacy and conservative character of the BWRVP-60 SCC Disposition Line 2 [11] for SCC crack growth in LAS during and 100 h after water chemistry transients ( Figure 1) and of the EPRI BWR Water Chemistry Guidelines (Table 1) [13] are evaluated and assessed in the context of the recent test results and literature data presented in the previous sections.…”
Section: Assessment Of Bwrvip-60 Scc Disposition Lines and Epri Watermentioning
confidence: 99%
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“…In the following paragraphs, the adequacy and conservative character of the BWRVP-60 SCC Disposition Line 2 [11] for SCC crack growth in LAS during and 100 h after water chemistry transients ( Figure 1) and of the EPRI BWR Water Chemistry Guidelines (Table 1) [13] are evaluated and assessed in the context of the recent test results and literature data presented in the previous sections.…”
Section: Assessment Of Bwrvip-60 Scc Disposition Lines and Epri Watermentioning
confidence: 99%
“…These lab experiments also formed the basis for the definition of disposition lines for crack growth due to SCC (Figure 1) which were proposed by the Electric Power Research Institute (EPRI) as an interim disposition rationale and subsequently accepted by the US NRC [11]. Disposition Line 1 (DL 1) considers crack growth under constant load in BWR environments during transient-free steady-state power operation.…”
Section: Introductionmentioning
confidence: 99%
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