Volume 1: Codes and Standards 2008
DOI: 10.1115/pvp2008-61870
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Historical Context of Elevated Temperature Structural Integrity for Next Generation Plants: Regulatory Safety Issues in Structural Design Criteria of ASME Section III Subsection NH

Abstract: In 2006, ASME and DOE signed a cooperative agreement to update and expand appropriate materials, construction and design codes for application in future Generation IV nuclear reactor systems that operate at elevated temperatures. The second task in this ASME/DOE Gen-IV Materials Project was to identify issues relevant to ASME Section III, Subsection NH, and related Code Cases that must be resolved for licensing purposes for VHTGRs (Very High Temperature Gas Reactor concepts such as those of PBMR, Areva, and GA… Show more

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Cited by 6 publications
(7 citation statements)
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“…As described earlier, high-temperature creep (and creep-fatigue) is expected to be mechanisms of concern in passive components in advanced reactors (O'Donnell et al 2008). Within the simplifieddesign being considered in this research, creep is expected to be of concern in vessel internals and in the materials comprising the heat-exchanger.…”
Section: Laboratory-scale High-temperature Creep Test Systemmentioning
confidence: 87%
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“…As described earlier, high-temperature creep (and creep-fatigue) is expected to be mechanisms of concern in passive components in advanced reactors (O'Donnell et al 2008). Within the simplifieddesign being considered in this research, creep is expected to be of concern in vessel internals and in the materials comprising the heat-exchanger.…”
Section: Laboratory-scale High-temperature Creep Test Systemmentioning
confidence: 87%
“…Specifically, the goal will be to examine primary and secondary stages of creep damage. The material of choice is austenitic stainless steel because of its anticipated wide use in several advanced reactor concepts (O'Donnell et al 2008).…”
Section: Assumptionsmentioning
confidence: 99%
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“…In particular, degradation (such as cracking, creep or creepfatigue damage) in passive components, if not addressed in a timely fashion, is likely to result in unplanned plant shutdowns. This is especially important for generally inaccessible passive components and key passive safety system components (such as heat exchanger tubing, primary boundary components, and reactor internals) (O'Donnell et al 2008). Thus, degradation in all passive components will need to be monitored and well-managed to maximize safety, operational lifetimes, and plant reliability while minimizing maintenance demands, if reduced economies-of-scale are to be overcome.…”
Section: Introductionmentioning
confidence: 99%
“…Other degradation mechanisms also become important when considering advanced reactor designs (O'Donnell et al 2008), including high-temperature effects on new materials such as 9Cr-1Mo steel. Each of these degradation types, as well as other degradation mechanisms that occur in these components, likely have different underlying mechanisms (many of which are poorly understood) that drive the accumulation of damage and initiation of cracking.…”
Section: Metalsmentioning
confidence: 99%